ML022970203
ML022970203 | |
Person / Time | |
---|---|
Site: | Braidwood |
Issue date: | 07/25/2002 |
From: | Caniano R, Grobe J Division of Reactor Safety III |
To: | Skolds J Exelon Generation Co, Exelon Nuclear |
References | |
50-456/02301, 50-457/02301 | |
Download: ML022970203 (279) | |
Text
INITIAL SUBMITTAL OF THE ADMINISTRATIVE JPMS FOR THE BRAIDWOOD INITIAL EXAMINATION - JULY 2002
JOB PERFORMANCE MEASURE TASK TITLE: Review Calorimetric Surveillance JPM No.: S-42a REV: 1 TPO No.: IV.C.NI-05 K&A No.: (015AI.01)
TASK No.: NI-004 K&A IMP: 3.5 /3.8 TRAINEE:
EVALUATOR:
DATE:
The Trainee: PASSED this JPM. TIME STARTED:
FAILED TIME FINISHED:
CRITICAL ELEMENTS: (*)3 JPM TIME: MINUTES CRITICAL TIME: NA APPROX COMPLETION TIME 10 MINUTES EVALUATION METHOD:
LOCATION:
x PERFORM IN PLANT SIMULATE X SIMULATOR GENERAL
REFERENCES:
- 1. lBwOSR 3.3.1.2-1, Rev. 6, Unit 1 Power Range High Flux Setpoint Daily Channel Calibration (Computer Calorimetric).
MATERIALS:
Copy of Completed/Ready for review 1BwOSR 3.3.1.2-1.
TASK STANDARDS:
- 1. Perform review of calorimetric data collected by NSO.
- 2. Verify the adjustment of NI's is correct.
- 3. Demonstrates the use of good Core Work Practices (CWP).
TASK CONDITIONS:
- 1. You are the Unit Supervisor.
- 2. The Unit 1 is at 100% power, steady state.
- 3. Unit 2 is at 100% power.
INITIATING CUES:
- 1. The Unit NSO has completed the required calorimetric surveillance and has asked for your review per 1BwOSR 0.1-1,2,3.
Note: Hand examinee completed calorimetric D-2 data sheet
- 1, with the 4 page printout of the calorimetric results from the JPN. (pages 6-9) 1 S-42 (7/3/01)
ZD73EXAM
PERFORMANCE CHECKLIST STANDARDS SAT UNSAT N/A RECORD START TIME Note: This JPM is performed by having the examine* review the D-2 Data shoot from the surveillance. The first data sheet is complete through block 15 but has 1 mistake in it.
The examinee must locate the mistake to pass the JPM prior to signing block 16, Review
,-_Authorization, and ending the JPM.
- 1. Refer to completed lBwOSR Review the data sheet for 0 03 03 3.3.1.2-1. completeness/errors for blocks 1 and 2:
(CUl: Ensure D-2 Data Sheet
- 1 is handed to
"* Date: Today examinee with the "* Time: 10 minutes ago printout of the "* Mwe Gross: Current calorimetric data.) (1257.0)
" Control Bank Position:
All Prereqs were met Current for Cl (228),
C2 (228), Dl (215), D2 (215).
"* NSOs Signature.
- 2. Review blocks 3,10,11 and Review blocks 3,10,11 and 13 12 for completeness 0 03 12.
and/or errors:
"* Initial NIS Drawer Front Panel Meter Power filled in.
"* Calculated Calorimetric Power from printout filled in.
"* Calculated Power difference filled in.
"* Block 12 checked (3 NO, 1 YES) 2 S-42 (7/3/01)
ZD73EXAM
PERFORMANCE CHECKLIST STANDARDS SAT UNSAT N/A
- 3. Verify the calculation DETERMINE the power that determines to what channel N-42 needs to be 0 0 0 power N-42 must be adjusted to as follows:
adjusted.
"o Ensure the present percent power values (Note: If examinee discovers are filled in block the N-44 mistake, and 13.
either wants the NSO to correct box 15 or "o VERIFY the corrected wants to do it calculated power himself, cue the difference from block examinee that the 11 in block 14.
correction has been made and hand him D-2 "o VERIFY/SUBTRACT the data sheet #2. power difference from the present indicated power and the value as (Note: The examinee needs to the Power to adjust verify the the NIS channels to in subtraction and block 15.
determination of the indicated power the " Identify that the adjustments must numbers were result in for N-44.) subtracted incorrectly (error) Correct answer should be i00.0%
(Note: If the examinee has " Sign the "Review NOT identified and Authorization", block corrected the mistake 16 after correction is (N-44) by the time he made to block 15.
signs Block 16, "Review Authorization-, and ends the JPM then the JPM performance is UNSAT.)
(CUE:) THIS COMPLETES THIS JPM.
RECORD STOP TIME COMMENTS:
3 S-42 (7,'3/01' Z D' 5FA".:
TASK CONDITIONS:
- 1. You are the Unit Supervisor.
- 2. The Unit 1 is at 100% power, steady state.
- 3. Unit 2 is at 100% power.
INITIATING CUES:
- 2. The Unit NSO has completed the required calorimetric surveillance and has asked for your review per IBwOSR 0.1 1,2,3.
S-42 (7/3/,01) 4 z DL-3 E:X AM
SIMULATOR SETUP INSTRUCTIONS 1PM NO: S-42 REQUIRED SIMULATOR MODE(S): 100% power steady state MALFUNCTION #'S: N/A COMMENTS:
- 1) Since the data sheets are already filled in, no further set up is necessary.
5 S-42 (71 3/01)
ZD-7 EXAM
( (
1BwOSR 3.3.1.2-1 Revision 8 Reference Use UNIT ONE COMPUTER CALORIMETRIC DATA SHEET
- 1. Date. --lo/ DA 14 Time: h1L 2!.3) 2 MWe (gross): Control Bank Positions: C1 . steps C2 U steps D1 Z-1 steps D2 5 steps ALL prerequisites have been satisfactorily addressed?: NSO Signature:
- 3. INITIAL NIS 10. Calculated 11. Calculate Power 12. Is an adjustment required?
Drawer Front Calorimetric Power = Dierence P"YES".if F. 11 > g% (+ or -) or is negative Panel Meter Power (From Printout) when above P-8]
NR-41 -,IQt*. = . 0 YES 0 NO NR-42 fe .O " in-, OYES E V NO NR-43 e- r YES 0 NO INR-44 -l YES 0 NO
- 13. PRESENT NIS 19. Was NIS Channel Drawer Front Panel 14. Calculated Power 15. PowertoAdjust 16. Review Satisfactorily Meter Power Difference (F.1 1) NIS Channel to Authorization Adjusted?
NR-42 W4A WA _ _A OYES
" YES 0fA/
O NO 0 NO NR-43 d:,,. AA, .4" D E N NR-44 Q9.4 0 YES O NO
- 22. a. Printout reviewed by Shift Manager or Designee? 0 YES 0 NO
- b. Printout attached on next data sheet? 0 YES 0 NO D-2 41'
(
1BwOSR 3.3.1.2-1 Revision 8 Reference Use UNIT ONE COMPUTER CALORIMETRIC DATA SHEET 1 Dateý -1b /D Time:646 AcA 2 MWe (gross): Control Bank Positions: C1 ZZ8 steps C2 11 A steps DI 125 steps D2 -7.S steps ALL prerequisites have been satisfactorily addressed?: NSO Signature:
- 3. INITIAL NIS 10. Calculated 11. Calculate Power 12. Is an adjustment required?
Drawer Front Calorimetric Power = rYES' if F. I1 > 2% (+ or-) or is negative Panel Meter Power (From Printout) Difference whnabove PF -r]
NR-41 i- o O = 0YES NR-42 - 10n 1 0_ YES WNO ONO NR-43 -- .- 1 - 0 YES 1NO SNR-44 X YES ONO
- 13. PRESENT NIS 19. Was NIS Channel Drawer Front Panel 14. Calculated Power 15. Powerto Adjust 16. Review Sasfaorily Meter Power Dierence (F11) NIS Chnnel to Auorizaton Adjusted?
NR-421 4A __ 0YES 0 NO NR-42 DAYES - NO NR-44 D 0 YES O NO 22 a. Printout reviewed by Shift Manager or Designee? DYES 0NO b Printout attached on next data sheet? D YES O NO D-2
(
1BwOSR 3.3.1.2-1 Revision 8 Reference Use UNIT ONE COMPUTER CALORIMETRIC DATA SHEET 2 MV~e (gross).-
Control Bank Positions:
Cl ZZ steps
- C2. :17 5k , steps D1 .. Z1.T P. 1 steps ALL prerequisites D2 - steps have been satisfactorily addressed?:
NSO Signature:
Drawer Front
- 3. INITIAL NIS 10. Calorimetric Cal lated Power =11. Calculate Power 1.I najsmn eurd P n et rff Printouta Prin toutD erorY ES "-if Fw1h> 2 % (+ o r -Do r is n eg a tiv e NR-42
- (
when above P-d8]
.3 -1 0 YES XI NO NR-43 C .**=
iNR-44 - -i-YES 13 I NO
- 13. PR.ESENT NIS J 13 YES 19 NO Drawer Front Panel 14. Calculated Power 15. Powerto Adjust 16. Review 19. Was NIS Channel Meter Power Difference (F.1 1) NIS Channel to Authorization Satisfactorily
- ,R4 ***Adjusted? 7hne
%,R-42
[ YES 0/ [] NO
- R4_*4 C0 *[
r22* a. Printout reviewed by Shit Manager YES [] NO or Designee-e]YS -- 2 b, Printout attached on next data sheet? YES NO
]N D YES 0] []
0ONONO 13 YES [] NO D-2
BRAIDWOOD UNIT 1 TIME: 10 MINUTES AGO TEN MINUTE AVERAGE CALORIMETRIC DATE: TODAY GROSS GENERATION: 1257.0 AVE NIS PR(%) 100.3 AVERAGE FEED WATER (DEGF) 443. 21 STEAM NET PRESS FEEDWATER BLOWDOWN INITIAL LOOP (PSIG) TEMPERING NIS FLOW (KBH) FLOW (GPM) THERMAL FLOW (KBH) POWER(%) POWER (KBTU/HR)
LOOP 1: 998.1 4008.89 58.26 41.31 100.3 3055.8 LOOP 2: 997.6 4020.04 58.18 41.06 99.1 3064.4 LOOP 3: 997.2 4021.15 58.18 41.85 100.1 3065.3 LOOP 4: 998.5 4004.22 58.29 41.97 99.6 3052.1 SUM LOOP THERMAL POWER (KBTU/HR): .1224E 05 PERCENT POWER (%): 100.0 6
BRAIDWOOD UNIT 1 CALORIMETRIC PAGE #2
'REREQUISITE TIME TOLERANCE AVERAGE DEVIATION SATISFIED?
- 1 REACTOR POWER 5 MIN - 0.5% 100.3 .0 YES
- 2 SG 1A LEVEL 5 MIN ÷/- 1.5% 60.0 .0 YES
- 2 SG 1B LEVEL 5 MIN +/ 1.5% 60.0 .0 YES
- 2 SG ID LEVEL 5 MIN ÷/ 1.5% 60.0 .0 YES
- 3 SG 1A PRESS 5 MIN +/- 1.0% 998.1 .0 YES
- 3 SG 1B PRESS 5 MIN +1- 1.0% 997.6 .0 YES
- 3 SG ID PRESS 5 MIN +/ 1.0% 998.5 .0 YES
- 4 NO ROD MOTION C 5 MIN +/- 0.2% 228.0 0.0 YES
- 4 NO ROD MOTION D 5 MIN +/ 0.2% 216 0.0 YES
- 5 S/G 1A BLWD FLOWS 5 MIN +/ 10% 58.3 .0 YES
- 5 S/G 1B BLWD FLOWS 5 MIN +/- 10% 58.2 .0 YES
.5 S/G IC BLWD FLOWS 5 MIN +/- 10% 58.2 .0 YES
- 5 S/G ID BLWD FLOWS 5 MIN +/ 10% 58.3 .0 YES
BRAIDWOOD UNIT 1 CALORIMETRIC PAGE #3
ý6 FEEDWATER FLOW SG lA TAP SET 1 5 MIN +/- 5.0% 488.2 0 YES SG IA TAP SET 2 5 MIN 5.0% 487.6 .0 YES SG 1B TAP SET 1 5 MIN 5.0% 491.0 .0 YES SG 1B TAP SET 2 5 MIN 5.0% 489.1 .0 YES SG 1C TAP SET 1 5 MIN 5.0% 487.2 .0
+1 YES SG 1C TAP SET 2 5 MIN 5.0% 485.9 .0 YES SG 1D TAP SET 1 5 MIN 5.0% 477.2
+1 .0 YES SG ID TAP SET 2 5 MIN 5.0% 481.9 .0 YES
+1 0.5% 443.2 .0 YES SG ID 5 MIN +/- 0.5% 443.2 .0 YES 8
BRAIDWOOD UNIT 1 CALORIMETRIC PAGE #4 TIME: 10 MINUTES AGO CALORIMETRIC INPUT SCAN STATUS 0 OF 88 CALORIMETRIC INPUTS ARE OFF SCAN
1BwOSR 3.3.1.2-1 Revision 8 Reference Use UNIT ONE POWER RANGE HIGH FLUX SETPOINT DAILY CHANNEL CALIBRATION (COMPUTER CALORIMETRIC)
A. STATEMENT OF APPLICABILITY This procedure outlines the steps necessary to perform a CHANNEL CALIBRATION of each OPERABLE Power Range Neutron Flux High Setpoint Channel by performing a secondary side computer calorimetric and verifying/adjusting the channel(s) as necessary. This procedure or 1BwOSR 3.3.1.2-2 SHALL be performed as applicable at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (normally performed twice) as directed by 1BwOSR 0.1-1,2,3 and is applicable in MODE 1 ' 15% RTP.
B. REFERENCES
- 1. Tech Spec LCO 3.3.1.
2 Tech Spec Surveillance Requirement SR 3.3.1.2, Table 3.3.1-1, Function 2.a.
3 Station Procedures:
- a. 1BwGP 100-3, Power Ascension.
- b. 1BwOSR 0.1-1,2,3, UNIT One MODES 1, 2 and 3 Shiftly and Daily Operating Surveillance.
- c. 1BwOSR 3.3.1.2-2, UNIT One Power Range High Flux Setpoint Daily Channel Calibration (Hand Calculated Calorimetric).
- d. 1 BwOL 3.3.1, LCOAR - Instrumentation - Reactor Trip System Instrumentation.
- 4. UFSAR Sections:
- a. 4.3.1.3. g. 10.4.9.32.
- b. 4.3.2.2.6 h. Table 14.2-82.
- c. 4.4.2.9.1. i. 15.0.7.
- d. 4.4.2.9.6. j. Table 150-6.
- e. 5 2.2 2. k. Table 15.6-2.
- f. 6.2.1.3.2.
- 5. ASME Steam Tables.
1
1BwOSR 3.3.1.2-1 Revision 8 Reference Use B. 6. Station Commitments/AIRs/etc.:
- a. 456-400-89-OP.02-01 D, define/address "suspect" values.
- b. 456-402-89-02301, notify SNE if Coarse adjustment was performed or if an adjustment of > 3% was made.
C. PREREQUISITES
- 1. Receive permission to perform this surveillance from the Shift Manager or designee prior to performance by having the Data Package Cover Sheet signed and dated IF being performed other than as directed by 1BwOSR 0.1-1,2,3.
- 2. Notify the Shift Manager or designee prior to performance of this surveillance if being performed as directed by 1BwOSR 0.1-1,2,3.
- 3. The Reactor has been at a constant power level > 15% of rated thermal power and the unit has been at a steady state load for greater than 10 minutes.
- 4. Steam Generator levels and steam pressures have been constant for greater than 10 minutes.
- 5. There has been no rod motion for greater than 10 minutes.
- 6. Feedwater flow and temperature have been constant for greater than 10 minutes.
- 7. Steam Generator Blowdown flows have been constant for greater than 10 minutes.
2
1BwOSR 3.3.1.2-1 Revision 8 Reference Use D. PRECAUTIONS
- 1. When using the process computer to perform the calorimetric calculation, care must be taken to verify that the steam generator blowdown flowrates are correctly input into the computer AT ALL TIMES. This must be done in order to verify the eight hour average power values are correct.
- 2. If any calorimetric manual input value is added, removed, or modified, a minimum of 15 minutes must elapse prior to initiation of the calorimetric to verify that the 10 minute historical calculation performed by the computer contains the new value(s) for the entire 10 minute calculated period. Field obtained manual inputs for feedwater pressure and feedwater temperature may be determined by the use of Appendix D.
- 3. UNIT operating parameters SHALL not be changed while performing the calorimetric or adjusting the NIS Power Range channels.
- 4. Data SHALL be obtained concurrently so that it is compatible.
- 5. Care should be taken when adjusting NIS Power Range channels to prevent an inadvertent Reactor trip due to an excessive rate of adjustment and/or failure to reset rate trips prior to adjusting subsequent channels.
- 6. The Calorimetric calculation should, whenever possible, be performed with the Tave - Tref deviation within 1 F, unless the Unit is in Coastdown. This is to verify that any required adjustments will result in more constant Nuclear Power indications when operating at or near 100% power.
E. LIMITATIONS AND ACTIONS
- 1. In the event the Acceptance Criteria is not met during the performance of this surveillance, IMMEDIATELY notify the Shift Manager or designee to initiate 1BwOL 3.3.1.
- 2. The computer printout must be signed by the Shift Manager or designee and attached to the last data sheet and retained.
- 3. All steps requiring recorded information SHALL be recorded in the specified blocks of the data sheets.
3
1BwOSR 3.3.1.2-1 Revision 8 Reference Use
- E. 4. The following applies to the QUALITY assigned to the values used in Plant Process Computer applications:
- a. SUSPECT (an "S" follows the value) means the data was not collected under optimal conditions or is the result of a manually entered input.
The value is acceptable.
- b. POOR (a °P" follows the value) means the value is marginal. Every effort must first be made to determine and correct the cause of a POOR final calorimetric output and the Shift Manager or designee must approve its use.
- c. BAD ("XXXX" is displayed in place of the value) means the value is unacceptable for use.
- d. The quality for each value is carried through any calculation using that value. The quality that appears is the worst quality that went into the calculation. The only exception is that a POOR combined with a SUSPECT or another POOR will result in a BAD quality.
- 5. An OPERABLE NIS Power Range Channel SHALL be adjusted if, based on the calorimetric:
- a. The absolute difference is greater than 2 percent, or
- b. When above P-8, the indicated power is less than that obtained in this calculation.
- 6. If the calorimetric indicates the need to adjust an OPERABLE NIS Power Range channel, this adjustment SHALL be accomplished promptly after the calorimetric calculation and prior to a power change.
- 7. If the process computer is unavailable, results must be obtained by performing 1BwOSR 3.3.1.2-2, UNIT One Power Range High Flux Setpoint Daily Channel Calibration (Hand Calculated Calorimetric).
- 8. If the Drawer Front Panel Meter for any Power Range Channel is inoperable it is acceptable to use the Main Control Board Indicator on 1PM05J for any required reading or adjustments.
- 9. If a Cold Junction T/C Reference input has failed (as indicated by BwAR 1-4-A6 and on the 1PM05J Monitor). exit this procedure and PERFORM 1BwOSR 3.3.1 2-2, Unit One Power Range High Flux Setpoint Daily Channel Calibration (Hand Calculated Calorimetric).
4
1BwOSR 3.3.1.2-1 Revision 8 Reference Use E. 10. If the Computer Room temperature and the Feedwater Inlet temperature computer points are noticeably trending in either direction at the same time, review the following sub-steps to determine if the calorimetric program is valid.
- a. Definitions Monitorinq Period: A Monitoring Period is defined as the period of time just prior to a Computer Room temperature change until the Room temperature stabilizes (less than 0.2 Deg F change in one hour) at a new value. This period may be up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> depending upon conditions.
Calorimetric Feedwater temperature points: T0418, T0438, T0458 and T0478.
Computer Room temperature points: T8004 and T8005.
- b. During a Monitoring Period, perform the following review:
5
1BwOSR 3.3.1.2-1 Revision 8 Reference Use NOTE It is recommended that the Operator review the following FW temperature trends:
The Calorimetric Feedwater Temperature Point, U0490, Stm Gen Feedwater In Avg T.
The RTD Feedwater Temperature Points U9030, Stm Gen in Avg RTD.
If a trending FW temperature is the result of actual Unit changes, this trend will be seen on both computer points.
If a trending FW temperature is the result of thermocouple compensation changes, only U0490, Stm Gen Feedwater Avg T will indicate the changing trend.
NOTE When the supplemental Air Conditioner (Liebert Unit) is started or shutdown the following indications are considered normal.
Liebert Unit started Calorimetric Feedwater Temperature approximate 0.6 Deg F increase over an approximate two hour period.
Liebert Unit shutdown Calorimetric Feedwater Temperature approximate 0.6 Deg F decrease over an approximate two hour period.
E. 10. b. 1) For the duration of a Monitoring Period, monitor the change in the Calorimetric Feedwater Temperature Points to determine Calorimetric validity:
Calorimetric Valid FW Temperature change less than 0.8 Deg F during the Monitoring Period.
Calorimetric May Be Invalid FW temperature change greater than 0.8 Deg F during the Monitoring Period, and the cause is due to the thermocouple compensation changes.
The calorimetric may be invalid. At the discretion of the Shift Manager/designee, exit this procedure and perform 1BwOSR 3.3.1.2-2, Unit One Power Range High Flux Setpoint Daily Channel Calibration (Hand Calculated Calorimetric).
Contact Engineering for additional guidance as required.
6
1BwOSR 3.3.1.2-1 Revision 8 Reference Use F. MAIN BODY
- 1. RECORD the date and time the calorimetric was started in Block 1 of Data Sheet D-2.
- 2. RECORD the gross megawatts electric and the control rod bank positions in Block 2 AND VERIFY that all PREREQUISITES (Section C) are satisfactorily addressed by signing in Block 2.
- 3. RECORD the Initial percent power readings from the NR-41, NR-42, NR-43, and NR-44 Drawer Front Panel Meters in Block 3.
- 4. SELECT OPCON Page:
O Verify OPCON Page showing at top center of computer.
O SELECT "OTHER" under "Page Section:" section at the left-center of computer screen.
- 5. POSITION mouse cursor to within the black background area to enable keyboard function.
- 6. DEPRESS "F8" to select function menu.
- 7. TYPE "23"
- 8. DEPRESS the "RETURN" key to select the computer calorimetric.
7
1BwOSR 3.3.1.2-1 Revision 8 Reference Use CAUTION Steam Generator Blowdown Flows can be manually entered, if necessary. All manually entered values must be verified correct and kept up to date so the eight hour average calorimetric is accurate. Also, any manually entered value that is added, removed, or modified, requires that a minimum of 15 minutes elapse prior to initiation of a 10 minute average calorimetric to ensure that calculation performed by the computer contains new value(s) for the entire 10 minute calculated the period.
F. 9. PERFORM the following to create a report:
- a. TYPE "2" as the time span (for a 10 minute average).
- b. SELECT the Report Format.
"O TYPE "1" as the Report Format for Short Output.
"O TYPE "2" as the Report Format for Long Output.
- c. SELECT desired output device.
"O TYPE "1'" for this CRT.
"O TYPE "2" for TREND TYPER.
- d. VERIFY each steam generator loop blowdown flow (If there is a problem with the flow sensor, then ENTER these values through point detail).
- e. DEPRESS RETURN.
- f. IF the printout percent power value QUALITY has an assigned code of "S" (SUSPECT), THEN perform a review of all manually entered process computer points in accordance with Appendix C.
(Otherwise this step is N/A) 8
1BwOSR 3.3.1.2-1 Revision 8 Reference Use F. 10. RECORD the percent power value for each OPERABLE Channel from the printout in Block 10.
- 11. DETERMINE the power difference using the formula below for each OPERABLE channel AND RECORD results in Block 11.
NIS Power Calorimetric Power Power Difference (Block 3) (Block 10) = (Block 11)
- 12. DETERMINE if an adjustment is required for each OPERABLE channel:
- a. IF Block 11 is a positive number and less than 2%, INDICATE "NO" in Block 12.
- b. IF Block 11 is greater than or equal to a positive or negative 2%,
INDICATE "YES" AND PROCEED to step 13.
- c. IF above P-8 and Block 11 is negative, INDICATE "YES" AND PROCEED to step 13.
- d. IF all answers are positive and less than 2%,
adjustments to NIS power range channels are not required but may be performed at the discretion of the Shift Manager or designee by proceeding to step 13.
- e. IF no adjustments are to be made, GO TO step 22.
- 13. RECORD the PRESENT percent power readings from the NR-41, NR-42, NR-43 and NR-44 Drawer Front Panel Meters in Block 13.
- 14. RECORD the POWER DIFFERENCE calculated in step 11 in Block 14.
- 15. SUBTRACT the Power difference (Block 14) from the current NIS readings (Block 13) to determine the indicated power level to adjust to and RECORD result in Block 15.
- 16. Power adjustment reviewed/approved by Shift Manager or Designee by signing in Block 16.
- 17. PLACE the Rod control system in MANUAL.
9
1BwOSR 3.3.1.2-1 Revision 8 Reference Use F. 18. Perform this step ONLY if one NIS Power Range Channel is Inoperable:
NOTE Verify the Tech Spec Action Statement for one inoperable Power Range channel is complied with.
- a. INSTALL the control power fuse for the inoperable channel.
NOTE The Lo RX Trip cannot be reset above 10% RTP.
- b. ADJUST the gain potentiometer (R303) on the inoperable NIS channel power range drawer B until the HI Rx trip bistable can be reset.
CAUTION The positive rate trips must be reset on the inoperable NIS channel prior to adjusting the gains on the operable channels. This will verify that a 2/4 Coincidence Reactor Trip will not occur.
- c. VERIFY/RESET any NIS Power Range RATE TRIP present.
- d. IF any of the applicable trip bistables cannot be reset, THEN DO NOT continue. NOTIFY the Shift Manager or designee.
- e. IF all of the applicable trip bistables are reset on the inoperable NIS channel, PROCEED to step 19 of this procedure.
10
1BwOSR 3.3.1.2-1 Revision 8 Reference Use F. 19. ADJUST the out of tolerance channels one at a time utilizing the following format:
CAUTION The following action could cause a Flux Rate Trip of the detector(s) being adjusted. Two of four channels will cause a reactor trip. Adjust one channel at a time.
NOTE Notify the Station Nuclear Engineer or designee as soon as practical thereafter if any channel requires an adjustment of, or is adjusted by more than 3% of Rated Thermal Power.
- a. ADJUST the GAIN potentiometer (R303) on Drawer B of the desired OPERABLE NIS Power Range to be adjusted until:
- 1) The PERCENT POWER reading agrees with the calculated value from Block 15, OR,
- 2) The GAIN potentiometer (R303) reaches the end of its adjustment range.
CAUTION DO NOT adjust the "coarse adjust" pots (R304 or R305) near the front left and right sides of the drawer.
These are the A and B ion current gain coarse level adjustments. Refer to Appendix A for location of R312.
NOTE Notify the Station Nuclear Engineer or designee as soon as practical thereafter if any channel requires a COARSE GAIN adjustment.
- b. IF the GAIN potentiometer (R303) reaches the end of its adjustment range. REQUEST IMD adjust the COARSE LEVEL ADJUST potentiometer (R312) such that:
- 1) The GAIN potentiometer (R303) is set approximately mid-range.
and
- 2) The PERCENT POWER reading agrees with the calculated value from Block 15.
11
1BwOSR 3.3.1.2-1 Revision 8 Reference Use F. 19. c. VERIFY/RESET any NIS Power Range RATE TRIP present.
- d. INDICATE "YES" in Block 19 for the channel adjusted.
- e. REPEAT Steps F.19.a, b, c, and d for any remaining OPERABLE NIS channels needing adjustment.
- f. IF the COARSE LEVEL ADJUST potentiometer was adjusted for any OPERABLE NIS Power Range Instrument, REPEAT this surveillance.
- 20. PERFORM this step ONLY if an inoperable NIS power range channel was restored in step 18 of this procedure:
- a. VERIFY/RESET the following bistables on the OPERABLE channels.
"* Hi Rx trip
"* Positive rate trip bý If the applicable trip bistables cannot be reset on the OPERABLE channels, then DO NOT continue and NOTIFY the Shift Manager or designee.
- c. IF the trip bistables are reset, THEN CONTINUE to the next step.
- d. REMOVE the control power fuse for the inoperable power range channel.
- e. VERIFY the following bistable tripped:
"* Lo Rx trip
"* Hi Rx trip
"* Positive rate trip
- 21. RETURN the Rod control system to AUTO when Tave is within 1 .0 F of Tef, or as directed by Unit Supervisor.
- 22. ATTACH the computer printout (reviewed by the Shift Manager or designee)
(with transparent tape) on the last data sheet and indicate "YES" in Block 22.
12
1BwOSR 3.3.1.2-1 Revision 8 Reference Use NOTE Notify the Station Nuclear Engineer or designee as soon as practical thereafter if any channel:
- 1. Requires a COARSE GAIN adjustment, or
- 2. Requires an adjustment of, or is adjusted by more than 3% of Rated Thermal Power.
G. ACCEPTANCE CRITERIA
- 1. Administratively limited to have, when above range instruments indicate or adjusted P-8, all OPERABLE NIS power to within a positive 2% reading of calculated thermal power of the calorimetric.
- 2. Limited by Tech Specs to have all OPERABLE NIS power range instruments indicate or adjusted to within a positive or negative 2% reading of calculated thermal power of the calorimetric.
13
1BwOSR 3.3.1.2-1 Revision 8 Reference Use APPENDIX A TOP VIEW OF POWER RANGE DRAWER "B"
CAUTION DO NOT adjust the "coarse adjust" pots (R304 or R305) near the front left and right sides of the drawer. These are the A and B ion current gain coarse level adjustments.
LEFT .'-ID)
T i l 1.,ý I1,':i(
0 0 0
\M :I();
\ \l :*()i;
\ (ý :,)() I
\\I jo()
N(ý :io.-, \ \f :*l.;
\M\ :iu
\i u
\M a * *000 000
- 0
- 0 I : I:: I
" M'.)\1 J. \
Pit ill sipj.
14
1BwOSR 3.3.1.2-1 Revision 8 Reference Use APPENDIX B (Page 1 of 3)
CALORIMETRIC PROGRAM INPUTS POINT ID DESCRIPTION UNITS NOTES F0407 S/G 1A BLOWDOWN F0427 S/G GPM 1B BLOWDOWN F0447 GPM S/G 1C BLOWDOWN F0467 GPM S/G 1D BLOWDOWN GPM F0417 S/G 1A BLOWDOWN F0437 S/G #2 TAP 1B BLOWDOWN F0457 S/G #2 TAP 1C BLOWDOWN F0477 S/G #2 TAP 1D BLOWDOWN
- 2 TAP F2239 S/G 1A FW TEMPERING F2240 S/G GPM 1B FW TEMPERING F2241 S/G GPM 1C FW TEMPERING F2242 S/G GPM 1D FW TEMPERING GPM U0415 STM GEN 1 NAR RNG L 1/2/3/4 AVG L0400 STM GEN PC 1 NAR RNG 1 L PC L0401 STM GEN 1 NAR RNG 2L L0402 STM GEN PC 1 NAR RNG 3 L PC L0403 STM GEN 1 NAR RNG 4 L PC U0435 STM GEN 2 NAR RNG L 1/2/3/4 AVG L0420 STM GEN PC 2 NAR RNG 1 L PC L0421 STM GEN 2 NAR RNG 2 L L0422 STM GEN PC 2 NAR RNG 3 L PC L0423 STM GEN 2 NAR RNG 4 L PC U0455 STM GEN 3 NAR RNG L 1/2/3/4 AVG L0440 STM GEN 3 NAR PC RNG 1 L PC L0441 STM GEN 3 NAR RNG 2 L L0442 STM GEN 3 NAR PC RNG 3 L PC L0443 STM GEN 3 NAR RNG 4 L PC U0475 STM GEN 4 NAR RNG L 1/2/3/4 AVG PC L0460 STM GEN 4 NAR RNG 1 L L0461 STM GEN 4 NAR PC RNG 2 L PC L0462 STM GEN 4 NAR RNG 3 L L0463 STM GEN 4 NAR PC RNG 4 L PC N0049 PWR RNG CH 41 (QUAD 4) DET 0 PC N0050 PWR RNG CH 42 (QUAD 2) DET 0 PC N0051 PWR RNG CH 43 (QUAD 1) DET 0 PC N0052 PWR RNG CH 44 (QUAD 3) DET 0 PC "These inputs are also used to determine the t# These inputs prerequisites affect QUALITY of Final Output of Calorimetric 15
1BwOSR 3.3.1.2-1 Revision 8 Reference Use APPENDIX B (Page 2 of 3)
CALORIMETRIC PROGRAM INPUTS POINT ID DESCRIPTION UNITS NOTES U0414 STM GEN 1 STM P 1/2/3 AVG P0400 PSIG STM GEN 1 STM OUT 1 P PSIG P0401 STM GEN 1 STM OUT 2 P PSIG P0402 STM GEN 1 STM OUT 3 P PSIG U0434 STM GEN 2 STM P 1/2/3 AVG P0420 PSIG STM GEN 2 STM OUT 1 P PSIG P0421 STM GEN 2 STM OUT 2 P PSIG P0422 STM GEN 2 STM OUT 3 P PSIG U0454 STM GEN 3 STM P 1/2/3 AVG P0440 PSIG STM GEN 3 STM OUT 1 P PSIG P0441 STM GEN 3 STM OUT 2 P PSIG P0442 STM GEN 3 STM OUT 3 P PSIG U0474 STM GEN 4 STM P 1/2/3 AVG P0460 PSIG STM GEN 4 STM OUT 1 P PSIG P0461 STM GEN 4 STM OUT 2 P PSIG P0462 STM GEN 4 STM OUT 3 P PSIG T0418 S/G 1A FEEDWATER IN TEMP DEGF ##
T0438 S/G 1B FEEDWATER IN TEMP T0458 DEGF S/G IC FEEDWATER IN TEMP DEGF T0478 S/G 1D FEEDWATER IN TEMP DEGF U0051 CONT ROD BANK C STEP COUNT U0052 STEPS CONT ROD BANK D STEP COUNT STEPS U0490 AVERAGE FEEDWATER TEMP DEGF U8020 S/G 1A RAW FW DP FT-510 U8021 INWC S/G 1A RAW FW DP FT-511 INWC U8022 S/G 1B RAW FW DP FT-520 U8023 INWC S/G lB RAW FW DP FT-521 INWC U8024 S/G 1C RAW FW DP FT-530 INWC U8025 S/G 1C RAW FW DP FT-531 INWC U8026 S/G 1D RAW FW DP FT-540 U8027 INWC S/G 1D RAW FW DP FT-541 INWC U1150 PWR RNG NUCL CHANNEL AVG T1MQ Q2800 PC GEN MW MW "These inputs are also used to determine the prerequisites
- These inputs affect QUALITY of Final Output of Calorimetric 16
1BwOSR 3.3.1.2-1 Revision 8 Reference Use APPENDIX B (Page 3 of 3)
CALORIMETRIC PROGRAM INPUTS POINT ID DESCRIPTION UNITS NOTES P0403 S/G 1A FW IN PRESSURE PSIG P0423 S/G 1B FW IN PRESSURE PSIG ##
P0443 S/G 1C FW IN PRESSURE PSIG P0463 S/G 1D FW IN PRESSURE PSIG ##
K8120 S/G 1A FT-510 FULL SCALE VALUE IN.WTR ##
K8121 S/G 1A FT-511 FULL SCALE VALUE IN.WTR K8122 S/G 1B FT-520 FULL SCALE VALUE IN.WTR K8123 S/G 1B FT-521 FULL SCALE VALUE IN.WTR K8124 S/G 1C FT-530 FULL SCALE VALUE IN.WTR ##
K8125 S/G 1C FT-531 FULL SCALE VALUE IN.WTR K8126 S/G 1D FT-540 FULL SCALE VALUE IN.WTR K8127 S/G 1D FT-541 FULL SCALE VALUE IN.WTR ##
K8100 FW VENTURI DESIGN CONSTANT ##
K8130 S/G 1A FW FLOW CALIB MULTIPLIER K8131 S/G 1B FW FLOW CALIB MULTIPLIER ##
K8132 S/G 1C FW FLOW CALIB MULTIPLIER ##
K8133 S/G 1D FW FLOW CALIB MULTIPLIER ##
K8140 BAROMETRIC PRESSURE (NOMINAL) PSIA ##
K8141 STM GEN STEAM QUALITY FRACTION ##
K8142 RCS PUMP + MISC HEAT (NOMINAL) MWT ##
K8143 STM GEN BLOWDOWN STATIC HEAD PSIA ##
K8144 RX RATED THERMAL POWER MWT ##
Note: The current values for the K81xx points above are also contained in the Operator Aid.
Feedwater Flow Constants. This table is updated as required by BwVP 850-20, "Feedwater Venturi Calibration".
These inputs are also used to determine the prerequisites.
- These inputs affect QUALITY of Final Output of Calorimetric.
17
1BwOSR 3.3.1.2-1 Revision 8 Reference Use APPENDIX C REVIEW OF MANUALLY ENTERED POINT VALUES This appendix outlines the steps to be taken at the HMI computer to call up a list of all that are manually entered into the Plant values Process Computer.
This review is required only when the QUALITY of the calorimetric final output has an assigned code of "S" (SUSPECT) to verify that the "S" is not the result of an inadvertent manual input.
An "S" code assigned to the calorimetric output value is fully acceptable. An "S" code assigned that is NOT the result of a manually entered to the calorimetric output that is the result known acceptable manually entered input of a is also fully acceptable.
To obtain a list of all manually entered values for the Plant Process Computer, perform following: the
- 1. SELECT OPCON PAGE:
O VERIFY OPCON page showing at top center O SELECT "Other" under "Page Section" sectionof computer.
at the left center of computer screen.
- 2. POSITION mouse cursor to within the black background area to enable keyboard function.
- 3. DEPRESS "F3" to select point review menu.
- 4. From "MENU OF POINT REVIEW FUNCTIONS",
SELECT:
Review Type: 8 (Entered Values)
Point Type: 1 (All)
System: 1 (All)
Device: 1 (This CRT) or 2 (Trend Typer)
Start. 1 (Beginning)
Stop: 1 (End)
- 5. DEPRESS "EXECUTE" (the report will take from 5 to 20 minutes).
- 6. REVIEW the report against the list of Calorimetric Program Inputs provided in Appendix B.
- 7. VERIFY that any manually entered values that affect the Calorimetric are correct for present plant conditions and that the value is supposed to be manually entered.
- 8. VERIFY that a minimum of 15 minutes has elapsed from the time any manual entry made to the time of initiation of the calorimetric. was (Final) 18
1BWOSR 3.3.1.2-1 Revision 8 Reference Use UNIT ONE COMPUTER CALORFMETRIC DATA SHEET Dateý ie MWe (gross):
Control Bank Positions:
C1 steps Dm C2 steps steps ALL prerequisites have been satisfactorily addressed?: NSO Signatures
- 3. INITIAL NIS
- 10. Calculated Drawer Front Calorimetric Power 11 Calculate Power 12. Is anajustment required?
Panel Meter Power (From Printout) = Difference ["YES",if F. 11 > 2% (+ or -)or is negative
"*JR-42 , I, when above P-81
- -- 1,.YES IV NO NR-43 N R-4413YES 0 YES 09 NO 09 NO Drawer Front Panel 14. Calculated Power 15. Powerlo Adjust 16. Review 19. a I hne Meter Power Difference (F.11) = NIS Channel to Authorization Satisfactorily Adjusted?
"%R-42 ,"
"_R-4 4 a- C- Y ES 22 a Printout reviewed by Shift Manager or Designee?NO r-Pint YES C3r1 N
NOO 00 YYES -CC3 NO NNO YESS
[0 D-2
BRAIDWOOD UNIT 1 TIME: 10 MINUTES AGO TEN MINUTE AVERAGE CALORIMETRIC DATE: TODAY GROSS GENERATION: 1257.0 AVE NIS PR(%) 100.3 AVERAGE FEED WATER (DEGF) 443.21 STEAM NET INITIAL LOOP PRESS FEEDWATER BLOWDOWN TEMPERING NIS THERMAL (PSIG) FLOW (KBH) FLOW (GPM) FLOW (KBH) POWER(%) POWER (KBTU/HR)
LOOP 1: 998.1 4008.89 58.26 41.31 100.3 3055.8 LOOP 2: 997.6 4020.04 58.18 41.06 99.1 3064.4 LOOP 3: 997.2 4021.15 58.18 41.85 100.1 3065.3 LOOP 4: 998.5 4004 .22 58.29 41.97 99.6 3052.1 SUM LOOP THERMAL POWER (KBTU/HR): .1224E 05 PERCENT POWER (%): 100.0
BRAIDWOOD UNIT 1 CALORIMETRIC PAGE #2
'REREQUISITE TIME J TOLERANCE AVERAGE "tIATION SATISFIED?
- 1 REACTOR POWER 5 MIN +/- 0.5% 100.3 .0 YES
- 2 SG 1A LEVEL 5 MIN +/- 1.5% 60.0 .0 YES
- 2 SG 1B LEVEL 5 MIN +/- 1.5% 60.0 .0 YES
- 2 SG ID LEVEL 5 MIN +1- 1.5% 60.0 .0 YES
- 3 SG 1B PRESS 5 MIN +/~ 1.0% 997.6 .0 YES
- 3 SG ID PRESS 5 MIN +/- 1.0% 998.5 .0 YES
- 4 NO ROD MOTION C 5 MIN +/- 0.2% 228.0 0.0 YES
- 4 NO ROD MOTION D 5 MIN +/- 0.2% 216 0.0 YES
- 5 SIG 1A BLWD FLOWS 5 MIN +/- 10% 58.3 .0 YES
- 5 S/G 1B BLWD FLOWS 5 MIN 10%
l/- 58.2 .0 YES 5 S/G IC BLWD FLOWS 5 MIN +/- 10% 58.2 .0 YES
- 5 S/G ID BLWD FLOWS 5 MIN + 10%
l- 58.3 .0 YES 7
53-4.2 .7/3/01)
Z 1) ,
- XA
BRAIDWOOD UNIT 1 CALORIMETRIC PAGE #3 J6 FEEDWATER FLOW SG 1A TAP SET 1 5 MIN +/- 5.0% 488.2 .0 YES SG IA TAP SET 2 5 MIN +/- 5.0% 487.6 .0 YES SG IB TAP SET 1 5 MIN +/- 5.0% 491.0 .0 YES SG lB TAP SET 2 5 MIN +/- 5.0% 489.1 .0 YES SG IC TAP SET 1 5 MIN +/- 5.0% 487.2 .0 YES SG 1C TAP SET 2 5 MIN +/- 5.0% 485.9 .0 YES SG 1D TAP SET 1 5 MIN +/- 5.0% 477.2 .0 YES SG ID TAP SET 2 5 MIN +/- 5.0% 481.9 .0 YES
- 7 FEEDWATER TEMPERATURE SG 1A 5 MIN +/- 0.5% 443.2 .0 YES SG 1B 5 MIN +0- 0.5% 443.2 .0 YES SG 1C 5 MIN +/- 0.5% 443.2 .0 YES SG ID 5 MIN +/- 0.5% 443.2 .0 YES 8
S-i2 (7/2/01) 77 'i.:'t -
BRAIDWOOD UNIT 1 CALORIMETRIC PAGE #4 TIME: 10 MINUTES AGO CALORIMETRIC INPUT SCAN STATUS 0 OF 88 CALORIMETRIC INPUTS ARE OFF SCAN 9
ci:
71
JOB PERFORMANCE MEASURE TASK TITLE: Review a QPTR Calculation
.PM No.: S-02QPTR REV: 0 TPO No.: IV.C.RK-01 K&A No.: 2.1.33 TASK No.: K&A IMP: 4.0 TRAINEE:
EVALUATOR:____________ DATE:
The Trainee: PASSED this JPM. TIME STARTED:
FAILED TIME FINISHED:
CRITICAL ELEMENTS: (*)7 JPM TIME: MINUTES CRITICAL TIME: NA APPROX COMPLETION TIME 15 MINUTES EVALUATION METHOD: LOCATION:
X PERFORM IN PLANT SIMULATE X SIMULATOR GENERAL
REFERENCES:
- 1. lBwOSR 3.2.4.1, Rev. 2, Unit One Quadrant Power Tilt Ratio (QPTR)
Calculation.
- 2. Operator Aid for 100% Power NIS Detector Currents.
MATERIALS:
- 1. 1BwOSR 3.2.4.1
- 2. Operator Aid for current values to be used in QPTR Calculation.
TASK STANDARDS:
- 1. Review QPTR Surveillance (lBwOSR 3.2.4.1)
TASK CONDITIONS:
- 1. You are the Unit Supervisor.
- 2. The Unit is at 100% power.
INITIATING CUES:
- 1. The NSO has completed and handed you a copy of lBwOSR 3.2.4.1 for you to review. The process computer and PDMS were inoperable for the purpose of this surveillance.
NOTE: Hand examinee completed QPTR surveillance lDwOSR 3.2.4.1 (D-3).
1
PERFORMANCE CHECKLIST STANDARDS SAT UNSAT N/A RECORD START TIME 4ote: This JPX is performed by having the examinee review the Data Sheet D-3, Unit 1 QPTR
._,alculation using NIS meters. The data sheet is complete but has one mistake in the calculation for Upper detector QPTR on N-42. The examinee must locate the error and determine the QPTR for channel 3-42 is outside the acceptance criteria.
- 1. Open and refer to 1BwOSR Open and refer to the 0 0l 0 3.2.4.1, QPTR Calculation. provided copy of lBwOSR 3.2.4.1.
(CUE: Ensure completed D-3 data Review the applicable shoot is handed to surveillance frequency examinee. for performance of this surveillance is once per 7 days:
All prerequisites, Limitations and actions "* PDMS is INOPERABLE were met for the "* Rx Power is >50%
performance of this "* NIS Power Range Tilts surveillance. alarm is OPERABLE The NIS Power Range Tilts "* QPTR has been within alarm is OPERABLE. limits (<1.02)
PDMB is inoperable.
Surveillance is performed as a normal weekly.
- 2. Review completed data Review data sheet D-3 for completeness/errors 0 0 E3 sheet D-3
"* Being completed once (CURE: If asked, the Unit has NO per normal interval LOCARs in progress at this "* Date (Today) time. "* Time (Now)
"* Channel reliable? (Y)
"* Instrument Readings properly recorded (100%)
- 3. Review Data sheet for Review Data sheet to ensure all present Upper 0 0 0 present and 100% detector currents and Lower Detector Currents are recorded as (CUE: All present and 100% well as all 100% detector values of Upper and Lower Upper and Lower currents.
Detector currents are accurate.
2
PERFORMANCE CHECKLIST STANDARDS SAT UNSAT N/A
- 4. Review the calculations to Review the Normalized Detector Currents for 0 0 0 obtain the normalized detector currents and each detector by dividing compare them to the its present detector calculated values on the current reading by the data sheet. 100% detector current value
"* Each Upper
"* Each Lower
- 5. Calculate and review the Review the Average Normalized Current by 0 0 3 average normalized currents and compare them summing the upper (lower) to the data sheet. normalized detector currents and dividing by 4 and compare this value to the Data Sheet:
"* Upper Average
"* Lower Average
- 6. Calculate and review the Review the QPTR for each detector by dividing each 0 0 0 QPTR for each detector and compare them to the QPTR Normalized Detector listed on the data sheet. Current by the Average Normalized Current and and compare this value to the data sheet:
"* Each Upper
"* Each Lower
- 7. Identify N42 Upper Identify N42 Upper Detector QPTR is >1.02 0 03 0 Detector QPTR is unacceptable. and is unacceptable.
(CUE: As SM acknowledge the 0 Initiate LCO 3.2.4.
required initiation of LCO 0 Inform SM of LCO entry 3.2.4.) requirement (CUE:) THIS COMPLETES THIS JPM.
RECORD STOP TIME COMMENTS:
3
TASK CONDITIONS:
- 1. You are the Unit Supervisor.
- 2. The Unit is at 100% power.
INITIATING CUES:
- 1. The NSO has completed and handed you a copy of lBwOSR 3.2.4.1 for you to review. The process computer and PDMS were inoperable for the purpose of this surveillance.
4 N-18 6/26/01
SIMULATOR SETUP INSTRUCTIONS JPM NO: S-02QPTR REQUIRED SIMULATOR MODE(S): NA MALFUNCTION #'S: N/A COMMENTS: Key (Page 6) should be reviewed. Upper half date of this sheet (Data sheet D-3) is given to the operators as is to review. This contains the calculation error for N42 upper detector.
The lower half data contains the correct calculations in bold type with the error that must be discovered for N42 upper detector.
5 N-18 6/26,01
UNIT ONE (KEY) QUADRANT POWER TILT RATIO CALCULATION (KEY)
NIS METERS
.3eing performed once per:
X 7 Days (normal interval) o Shiftly 0 12 Hours (with BwVSR 3.2.4.2.) 14 Other: P0~4S, ;*kk93,t2l Date: TODAY Time: NOW (Data sheet given to SRO for review)
Channel N41 N42 N43 N44 Is the channel operable? lQY ON IXY ON OY ON MY ON Instrument reading 100% 100% 100% 100%
UPPER DETECTORS (A)
Present upper detector current 192 187 190 185 100% upper detector current 194 181 192 186 Normalized detector current .990 1.01 .990 .995 Average normalized current .996 Upper power tilt ratio (0<1.02) .994 1.01 .994 .999 LOWER DETECTORS (B)
Present lower detector current 170 150 165 165 100% lower detector current 170 153 165 168 Normalized detector current 1.00 .980 1.0 .982 Average normalized current .991 Lower power tilt ratio (0<1.02) 1.01 .989 1.01 0.991 Date: Time: (Data sheet with correct calculations - error on N-42)
Channel N41 N42 N43 N44 Is the channel operable? MY ON MY ON MY ON 01Y ON Instrument reading 100% 100% 100% 100%
UPPER DETECTORS (A)
Present upper detector current 192 187 190 185 100% upper detector current 194 181 192 186 Normalized detector current .990 1.03 .990 .995 Average normalized current 1.00 Upper power tilt ratio (<1.02) # .990 $ 1.03 $ .990 0 .995 LOWER DETECTORS (B)
Present lower detector current 170 150 165 165 100% lower detector current 170 153 165 168 Normalized detector current 1.00 .980 1.00 .982 Average normalized current .991 Lower power tilt ratio (<1.02) 1.01 0 .989 0 1.01 0 .991 Attach additional copies of this page as necessary.
6 N-18 6/26/01
1BwOSR 3.2.4.1 Revision 2 Reference Use UNIT ONE QUADRANT POWER TILT RATIO (QPTR) CALCULATION A. STATEMENT OF APPLICABILITY This procedure outlines the steps necessary to verify the QUADRANT POWER TILT RATIO is*< 1.02. It is applicable in MODE 1 above 50% RATED THERMAL POWER when the Power Distribution System (PDMS) is inoperable and shall be performed:
- 1. Once per 7 days.
- 2. Once per shift when the NIS Power Range Tilts alarm is INOPERABLE as directed by 1BwOL 3.2.4 and 1BwOSR 0.1-1,2,3.
- 3. Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when QUADRANT POWER TILT RATIO is not within limits as directed by LCOAR 1BwOL 3.2.4.
B. REFERENCES
- 1. Tech Spec LCO 3.2.4.
- 2. Tech Spec Surveillance Requirements:
- a. 3.2.4.1.
- b. 3.2.4.2.
- 3. TRM TLCO 3.3.h.
- 4. Station Procedures:
- a. 1BwOSR 0.1-1,2,3, Unit One MODES 1,2 & 3 Shiftly & Daily.
- b. 1BwOL 3.2.4, LCOAR - Power Distribution Limits - QPTR.
- c. 1BwOL TRM 3.3.h, Technical Requirements Manual (TRM) LCOAR Power Distribution Monitoring System (PDMS)
- d. BwVSR 3.2.4.2, QPTR Checkout Using Incores.
1
1BwOSR 3.2.4.1 Revision 2 Reference Use B. 5. Station Commitments:
- a. 456-200-87-38101, limitation to check the operability of the QPTR Alarm anytime QPTR exceeds 1.02.
- b. 456-130-98-3.2.4-0100 "Specific SAR Commitment" (Regarding shiftly surveillance interval when the power range tilts alarm is inoperable).
C. PREREQUISITES
- 1. Receive permission to perform this surveillance from the Shift Manager or designee prior to performance by having the Data Package Cover Sheet signed and dated.
- 2. Reactor power should be constant while recording NIS data.
- 3. The latest 100% Power NIS Detector Currents are available (from Station Nuclear Engineer or Operator Aid).
D. PRECAUTIONS None.
2
1BwOSR 3.2.4.1 Revision 2 Reference Use E. LIMITATIONS AND ACTIONS
- 1. As stated in Tech Spec LCO 3.2.4.
- 2. In the event the Acceptance Criteria () is not met during the performance of this surveillance, IMMEDIATELY notify the Shift Manager or designee to initiate LCOAR 1BwOL 3.2.4.
- 3. Anytime the calculated QPTR exceeds 1.02, the NIS Power Range Tilts alarm OPERABILITY should be reviewed. If the alarm is not illuminated the required frequency of this surveillance shall be increased from once per 7 days to once per shift in accordance with 1BwOL 3.2.4.
- 4. The process computer point calculation is the most accurate method of calculating QPTR and should normally be used. During the performance of AFD calibrations on the excore detectors the process computer point method will not be correct until ALL drawers are calibrated. During this calibration period QPTR MUST be calculated using the NIS meter method.
- 5. If the Power Range channel is inoperable but individual detector current indication is reliable, performance of BwVSR 3.2.4.2 is not required. Detector current indication can be considered reliable if detector degradation or failure is not indicated, the detector signal cable is attached to the 1PM07J drawer, and proper high voltage is applied to the detector. In this condition, the QPTR alarm may be inoperable but the neutron flux input to QPTR is available. QPTR can be calculated using the individual detector current meter indications.
3
1BwOSR 3.2.4.1 Revision 2 Reference Use F. MAIN BODY
- 1. VERIFY all applicable Prerequisites, Precautions, and Limitations and Actions are satisfactorily addressed.
- 2. INDICATE the applicability of this surveillance on the appropriate Data Sheet (REFER to Statement of Applicability):
- a. Being performed once per_7 days.
- b. Being performed once per shift.
- c. Being performed once per 12 hrs with BwVSR 3.2.4.2.
- d. Other (Specify).
- 3. RECORD the Date and Time.
NOTE With one Power Range Channel INOPERABLE and THERMAL POWER is > 50% but < 75%, the QPTR may be calculated using the three OPERABLE channels. With one Power Range channel input to QPTR INOPERABLE with THERMAL POWER > 75%, the QPTR shall be calculated using the three OPERABLE channels taking data when directed by System Engineering during performance of BwVSR 3.2.4.2. RECORD "N/A" for the INOPERABLE Power Range channel data.
- 4. RECORD the OPERABILITY status and indicated Reactor Power from the NIS drawer front panel PERCENT FULL POWER meters on the appropriate Data Sheet.
4
1BwOSR 3.2.4.1 Revision 2 Reference Use NOTE Step F.5 and F.6 are independent of each other. Perform the applicable step.
Step F.5 will use the process computer to determine the QPTR.
Step F.6 will use installed NIS Meters or DVMs to determine QPTR.
F. 5. DETERMINE the QPTR using process computer points as follows (N/A if determined with the NIS meters):
- a. RECORD present computer point reading.
- b. DIVIDE the sum of the computer points by the number of operable channels to obtain the average computer point reading.
Average Computer Sum of Computer Points Point Reading Number of Operable NIS Channels
- c. DIVIDE the Computer Point Reading by the Average Computer Point Reading to determine the Quadrant Power Tilt Ratio.
Power Tilt Ratio Computer Point Reading Average Computer Point Reading 5
1BwOSR 3.2.4.1 Revision 2 Reference Use F. 6.0 DETERMINE the QPTR using installed NIS Meters or DVMs NOTE Step 6.a will install DVMs, N/A step if using installed NIS Meters.
Step 6.b will determine the QPTR using installed NIS Meters or DVMs.
Step 6.c will remove DVMs, N/A step if using installed NIS Meters.
NOTE The following annunciator(s) may actuate during connection of the DVMs. This list is not all inclusive but if the annunciator(s) does not reset when the DVM is disconnected, investigate the cause before going to the next drawer.
1OA04PWR RNG UPPER DET FLUX DEV HIGH 1OB04PWR RNG LOWER DET FLUX DEV HIGH 10C04PWR RNG CHANNEL DEV 1OB05PWR RNG FLUX HIGH ROD STOP Tomnmz h fetCAUTION To minimize the effect of meter loading to the drawer, Fluke 8840A DVMs shall be used. If there are not enough 8840As available, Fluke 8505A and Fluke 8502 may be substituted. Other DVM may also be used with the consent of NIS System Engineer or backup. In addition, shielded test leads shall be used to avoid EMF induction to the reactor protection system circuitry.
CAUTION A Reactor Trip could occur if a 2 of 4 coincidence is made up due to a channel trip on the power range detector being measured. The DVM MUST be initially set to the millivolt range for detector current readings to prevent a channel trip.
If the current as seen on the face meter is low (at low powers), it is permissible to down range the detector meter current selector switch for better resolution.
6
1BwOSR 3.2.4.1 Revision 2 Reference Use CAUTION Ensure that the DVM leads to be used have no flaws in their insulation. Also ensure that any contact points between the leads and the drawer are properly protected to ensure that chafing of the leads' insulation does not occur. If the DVM leads become shorted to ground after connection, the associated power range channel will be made inoperable.
- CAUTION Power range cables can become snagged while opening the drawers. Open the rear cabinet doors to 1PM07J and station a person at the rear of the drawers to ensure that all cables are free while opening the drawer.
Minimize motion of the cables, since the cable may become disconnected from its connector if excessive motion occurs. This could make the drawer inoperable.
F. 6. a. NOFITY IMD to perform the following for each Power Range "B" drawer:
- 1) CAREFULLY OPEN the Power Range Nuclear Instrumentation Channel "B drawer.
- 2) CONNECT a DVM between the red and black test jacks of the detector current meter for each of the eight Power Range detectors.
- 3) ROLL the Power Range "B" drawers carefully as far into the 1PM07J panel as possible. Avoid crimping or damaging the DVM leads. If possible, slightly engage the seismic screws on the front of the drawers.
7
1BwOSR 3.2.4.1 Revision 2 Reference Use F. 6. b. DETERMINE the QPTR using NIS meters or DVM as follows (N/A if determined with the computer points):
- 1) RECORD each present detector current.
- 2) RECORD the latest 100% Power NIS detector current (from the Station Nuclear Engineer or the Operator Aid).
- 3) DIVIDE the present detector current by the 100% detector current to obtain the normalized detector current.
Normalized Present Detector Current Detector Current 100% Detector Current
- 4) DIVIDE the sum of the normalized detector currents by the number of operable channels to obtain the average normalized current.
Average Sum of Normalized Detector Currents Normalized Current Number of Operable NIS Channels
- 5) DIVIDE the Normalized Detector Current by the Average Normalized Current to determine the Quadrant Power Tilt Ratio.
Normalized Detector Current Power Tilt Ratio Average Normalized Current 8
1BwOSR 3.2.4.1 Revision 2 Reference Use F. 6. c. PERFORM the following to RESTORE each Power Range "B" Drawers:
NOTE The following steps are applicable if DMVs are to be used to indicate detector current. Mark this section N/A if current meters installed in the drawers are to be used.
CAUTION Power Range cables can become snagged while opening the drawers. Open the rear cabinet doors to 1PM07J and station a person at the rear of the drawers to ensure that all cables are free while opening the drawer. Minimize motion of the cables, since the cable may become disconnected from its connector if excessive motion occurs. This could make the drawer inoperable.
- 1) CAREFULLY OPEN the Power Range "B" drawers.
- 3) CAREFULLY CLOSE and SECURE the Power Range "B" drawers.
- 4) REMOVE all material installed to secure equipment.
G. ACCEPTANCE CRITERIA No Quadrant Power Tilt Ratio shall exceed 1.02.
(Final) 9
1BwOSR 3.2.4.1 Revision 2 Reference Use UNIT ONE QUADRANT POWER TILT RATIO CALCULATION COMPUTER POINTS NOTE The proc* computer point calculation is the most accurate method of calculating QPTR and ould normally be used. During the performance of AFD calibrations on the excor detectors the process computer point method wil not be correct until SALL drawer acalibrated. During this calibration period QPTR MUST be calculated usln NIS meter method.
Being perfomed orqos pq o 7 Days (normal Interval) O ShifUy o 12 Hours (with BwVSR 3.2. .2) O Other:
Date: Time:
Channel; N41 N*42 N43 N4
=Is the channel operabe?' OY ON 0-Y O]N OY ON []Y ON befctrs(A)
C-_ 2,.- N0041 N0043 N0045 Pr**es-nt com,-puterpoint reading\ N0047 Average computer point reading Upper rp,"
tilt ratio JjE;1.02) d To 10 Comute pon N04 LowerPn tr tctorr (B) 0044 N0046 N0048 Prewsent computer point reading Average computer point readingl Lowev r Dower tilt ratio (051.02) 0 To-#I Date: Time:
Channel N41 N42 N43 N44.
Is the channel operable? I"1 1\Y ON 0N I 'Oy O]N 1Y nN O Instrument reading % %I %I %
Compuer pint pper Detectors (A) N0 IPresent computer ni-Anf roafin x l l "A.- -I I I Puyuga Computr point readino
- I-...- *:*. ,A Upperoe .nu olt ratio W-1*].02)
\¢ 0
otiJ~uuputur pJ LOwer Detect-
- 7RI N0042 N0044 I\ N 0046. I N0048 resent computer point reading I I\
Average computer poin treading-"
Lower powertilt ratio (- !01.02) I\I ATTACH additional copies of this page as necessary. \ /A D-2
1BwOSR 3.2.4.1 Revision 2 Reference Use UNIT ONE QUADRANT POWER TILT RATIO CALCULATION NIS METERS Being performed once per:
JK 7 Days (normal interval) O Shiftly 0 12 Hours (with BwVSR 3.2.4.2) O Other:
Date: -rbOWA Timne: 140y4 Channel N41 N42 N43 N44 Is the channel indication reliable? 41Y ON MY ON MY ON MY ON Instrument reading i10.o % 100.0 % (gO0. % 100.0 %
Upper Detectors (A)
Present upper detector current 2-2- Pal l 1 qO 9,5 100% upper detector current q I 18 I (q - 18()
Normalized detector current qO I09.01 qq0 ** :5 Average normalized current * 'qqg Upper power tilt ratio ($:91.02)
- qq I e.0l
- qq I* qqc Lower Detectors (B)
Present lower detector current I170 IISO
-0 I I IkyS 100% lower detector current I-1t I 1s, I f(S I 1n8 Normalized detector current I 000
- q80 Average normalized current
- gg j Lower power tilt ratio (0-1.02) I 10 , 1.01 Date: Time:
Channel N41 N42 N43 N44 Is the channel indication reliable? QY ON Oy ON OY ON OY ON Instrument reading % % % %
Upper Detectors (A)
Present upper detector current 100% upper detector current Normalized detector current Average normalized current Upper power tilt ratio (0<-1.02)
Lower Detectors (B)
Present lower detector current 100% lower detector current Normalized detector current Average normalized current Lower power tilt ratio (0<_1.02)
ATTACH additional copies of this page as necessary.
D-3
1BwOSR 3.2.4.1 Revision 2 Reference Use UNIT ONE DVM CALIBRATION TABLE DVM Cal Date Due Date Initials IV N41 Top Bottom N42 Bottom TOP " L ,i ..
N43 Top Bottom _ ._
N44 TOP "
Bottom ._"
DVM Leads Installed Leads Removed. IV Name/Date Naml te Name/Date Name/Date N41 A Bottom N42 To0 _,. __
N43T
_44 To_ _ __ _ __ _
I Bottom (Final)
D-4
PERFORMANCE CHECKLIST STANDARDS SAT UNSAT N/A JOB PERFORMANCE MEASURE TASK TITLE: Approve BDPS First Hang JPM No.: S-02BDPS REV: 0 TPO No.: K&A No.: 2.1.33 TASK No.: K&A IMP: 3.8 TRAINEE:
EVALUATOR:____________ DATE:
The Trainee: PASSED this JPM. TIME STARTED:
FAILED TIME FINISHED:
CRITICAL ELEMENTS: (*)5 JPM TIME: MINUTES CRITICAL TIME: NA APPROX COMPLETION TIME 11 MINUTES EVALUATION METHOD: LOCATION:
X PERFORM IN PLANT SIMULATE X SIMULATOR
'GENERAL
REFERENCES:
- 1. 1BwOSR 3.9.2.1 Refueling BDPS Monthly Surveillance
- 2. lBwOL 3.3.9 BDPD Tech Spec - Modes 3,4 or 5 MATERIALS:
Copy of BDPS First Hang Clearance Order TASK STANDARDS:
- 1. Perform review of First Hang Clearance Order
- 2. Determine if Clearance Order is complete and ready to hang TASK CONDITIONS:
- 1. You are the Unit Supervisor.
- 2. Unit 1 is in Mode 5.
- 3. Preparations are being made for Mode 6 entry next shift.
INITIATING CUES:
- 1. The Shift Manager has assigned you the review and 2' approver task for the BDPS First Hang Clearance Order for BDPS.
Note: When performing this JPM in the simulator, access to EWCS is not available.
Normally, approvals are electronic via EWCS. This JPM will simulate the process.
1 N-
JOB PERFORMANCE MEASURE TASK TITLE: Review a Liquid Release Package.
JPM No.: 8-41 REV: I TPO No.: VIII.C.HP-001 K&A No.: (G2.3.6)
TASK No.: S-HP-001 K&A IMP: 2.1 / 3.1 TRAINEE:
EVALUATOR:
DATE:
The Trainee: PASSED this JPM. TIME STARTED:
FAILED TIME FINISHED:
CRITICAL ELEMENTS: (*) 3 JPM TIME: MINUTES CRITICAL TIME: N/A APPROX COMPLETION TIME 10 MINUTES EVALUATION METHOD: LOCATION:
x PERFORM IN PLANT SIMULATE x SIMULATOR GENERAL
REFERENCES:
"1. BwOP WX-501Tl,Rev. 19, "Liquid Release Tank OWX01T release Form."
MATERIALS: Copy of BwOP WX-501T1 (filled in through step E.11).
TASK STANDARDS:
- 1. Complete review of Operations section E of BwOP WX-501T1.
- 2. Demonstrates the use of good Core Work Practices.
TASK CONDITIONS:
1.
2.
You are the Control Room Supervisor.
All plant systems and controls are normal for the current plant conditions.
INITIATING CUES:
- 1. Liquid Release package paperwork L-02-049 is complete through step E.11, and is ready for your review.
- 2. The SM has directed you to review and sign section E as applicable, and inform him of the results of your review.
Note: Hand Section 3 of the partially completed package to the examinee.
S-41 (7/2/01)
ZD73EXAM
PERFORMANCE CHECKLIST STANDARDS SAT UNSAT N/A Note: Hand BDPS first hang clearance order to examinee RZCORD START TIME
- 1. Refer to completed First Review First Hang for 0 3 0 Hang Checklist (001) completeness/errors
(#99006844) "* Prepared By
"* lt Approver
"* Special Instructions
- 2. Refer to Tech Spec 3.3.9 Locate and Open Tech Spec 3.3.9 0 0 0 for applicability review
"* Review applicability for performing this First Hang
"* Applicable in Mode 6
- 2. Refer to Tech Spec 3.3.9 Locate and Open Tech Spec 3.3.9 Basis. Review for 3 0 03 Basis document valves to be included and required valve positions.
- 3. Review Basis document for Determine the following 3.3.9. valves are applicable o 0 0 and must be secured in the closed position
"* 1CV111B
"* 1CV8428 0 1CV8441 0 1CV8435 0 1CV8439
- 5. Review First Hang for " Determine the First 0 0 0 completeness and accuracy Hang to be incomplete.
(Cue: After examines identifies "* As US do NOT sign as the clearance order is 2d Approver inc=Wlete, ask what is "missing if not provided by "* Determine the examinee.
following valves have not been included in After the missing valves the First Hang for are identified, hand the BDPS missing sheet (page 2) to "* 1CV8441 the examinee. "* 1CV8435 2
N-
PERFORMANCE CHECKLIST STANDARDS SAT UNSAT N/A
- 6. Approve the BDPS First Hang Determine First Hang is 0 0 0 now accceptable and verbalize approval.
(CUB:) THIS COXPLUTZS THIS JiPM.
RUCORD STOP TINZ COMMENTS:
3
TASK CONDITIONS:
- 1. You are the Unit Supervisor.
- 2. Unit 1 is in Mode 5
- 3. Preparations are being made for Mode 6 entry next shift INITIATING CUES:
- 1. The Shift Manager has assigned you the review and 2" approver task for the First Hang Clearance Order for BDPS.
4 N-
I I*IMIw !CKLIST : 001 99006844 "FIRST HANG UNIT:
HN-. H ANG HANG PAGE: 2 ISOLATION POINT BY VER I LIFTI LIFT LIFT LOCATION & DESCRIPTION LIFT HANG C/O-RD SEQ POS BY 004 L/C EMERGENCY BORATION LINE FLUSHING VCVE441 WiT ISOL VLV I
VCT VLV AISLE 0000043854 426 16 Q AUX ECODE:
HANG 034 C/O-RD
/
L/C ICV8435 CV CHEM MIXNG TNK OUTLET VCT VLV AISLE I
- - 0000043850 426 16 Q AUX ECODE:
END OF ISOLATION POINTS
SIMULATOR SETUP INSTRUCTIONS JPM NO: N-27B REQUIRED SIMULATOR MODE(S): NA MALFUNCTION #'S: N/A COMMENTS:
5
i~l*iilii*'misw 001IT:oo 99006844 UNIT:
FIRST HANG PAGE:
7AS ALT TAG:
AS.LY Eýtjtp: NAME: &DIPSADMIN WORK DESC: BWPS ADMIN CONTROL PER TS 33.9 MC \oc2: 01 A 24 SPECIAL INST: PER IBWOSR3.92.i REUELINGDILUTONPRIEVENTION PRE!ARED BY: D R MLADIC VALVE POSION MONTI SUETECH SPP: V R GUINTO SPEC APPLICA*ILE IN MODE 6 AND IS PERFORMED 2N' APPR: MONTULy OR AS REQD BY LCOAR INWOL 33.9 IN MODES 3.4, Oft S.
AU'TH BY:
HAI,' HANG HANG HANG POS ISOLATION POINT BY VER LIFTI LIFT LIFT LOCATION & DESCRIPTION LIFT SEQ POS BY VER HANG NO-CARD 001 N/A SPECIAL INSTRUCTIONS REVIEWED/COMPLETED ECODE:
HANG C/O-CD I PMOSJ-B2-254 002 CLOSED ICV! I IB C/S AB BLENDER INJECTION VLV TO VCT I PMo5J c"__ : 0000390340 451 10 L AUX MCR ECODE:
HANG C/O-RD ICVII IlB-'A 003 CLOSED ICVIIIB VA ICV! IIIB I/A SUPPLY ISOL VLV VCT VLV AISLE ECOD E 0000042900 426 16 Q AUX ECODE:
HANG C/O-RD 004 L/C ICV8428 BA BLENDER TO CHG PMPS ISOL VLV I
EC: -:0000043843 426 16 Q AUX CVVLV ECODE:
HANG C/O-RD 004 ICV8439 L/C BA FCV TO VCT OUTLT HDR ISOL VLV VCT VLV AISLE 426 16 Q AUX CVVLV 1:U 4 3 ECODE:
C.! : 7 B.Y : DATE: TIME:
lilli[. REVIEW
! £CKLIST: 001 99006844 UNIT: (
FIRST HANG PAGE: 3
ý'.ZEA.ANCE ORDER HOLDERS:
HcIýez Holder Name Discipline -- Accepted--- ---- Released ----- Auth. By Extension DR%%11S %MAR Or 2091
- * *
- END OF REPORT * * *
- PERFORMANCE CHECKLIST STANDARDS SAT UNSAT N/A RECORD START TIMN
- 1. Refer to partially Reads Step E.12, notices 0 0 13 completed BwOP WX-501T1, no signature (yet) and Section E.12. turns back to beginning of section E (page 19).
(CUR:
- 2. Reviews steps E.1-7. Reviews steps E.1-7: 0 0 0
"* Step 1 time and date.
"* Step 2 signed and dated by CRS.
"* Steps 3 initialed
"* Steps 4 initialed and Low Flow circled
"* Steps 5&6 initialed and values filled in for alarm setpoints.
(CUR: Daily channel checks are completed) "* Step 7 initialed.
- 3. Determines step E.8 should Review steps E.8 and E.9 3 be completed and is not.
0 0 Determines release may not be performed:
- Step E.8 is NOT (CUR As SN, ask what is performed as required wrong with the for Low Flow releases.
paperwork. After the examinee states the "o Step E.9 IS performed interlock check for but should not be.
the low flow release "o Steps E.8 and E.9 are path was not swapped. Interlock performed correctly, checks performed on conclude the JPM. wrong component(s) for Low Flow release.
"* Informs SM release paperwork was not performed properly.
"* Does NOT sign step E.12.
(CUE:) THIS COMPLETES THIS JPM.
RECORD STOP TIME
-'OMMENTS:
2 S-41 (7/2/01)
ZD73EXAM
TASK CONDITIONS:
- 1. You are the Control Room Supervisor.
- 2. All plant systems and controls are normal for the current plant conditions.
INITIATING CUES:
- 1. Liquid Release package paperwork L-02-049 is complete through step E.11, and is ready for your
- 2. The SM has directed you to review and signreview.
section E as applicable, and then inform him of the results of your review.
3 S-41 (7/2/01)
ZD73EXAM
SIMULATOR SETUP INSTRUCTIONS JPM NO: S-41 REQUIRED SIMULATOR MODE(S): 1.
MALFUNCTION #'S: N/A COMMENTS:
- 1) The alarm setpoints and background values in the release package paperwork may be different than the numbers in the simulator. If they are and will invalidate this JPM, then an IC must be made that has the numbers the same as the paperwork. The numbers of concern are:
Paqe O4m Rad monitorR n M =WW^1 12 .D.4 ORE-PRO01 2. 01E-5 1.60E-7 12.D.5 'I 15.D.7.a 1.60E-7 15.D. 7.a High stpt 1. 31E-4 6.38E-4 15.D.7.a Alert stpt. 6.56E-5 3. 19E-4 15.D.7.b chan 9 hi 1. 31E-4 6. 38E-4 15.D. 7.b chan 10 Al 6.56E-5 3.19E-4 16.D. 8 .a OPRO10 cur 8.12E-7 9. 99E-7 16.D.8.a High stpt 8.19E-6 1.20E-5 16.D. 8 .a Alert stpt. 5.73E-6 5. 8E-6 16.D.8.b chan 9 hi 8.19E-6 1.20E-5 16.D. 8 .b chan 10 Al 5.73E-6 5.8E-6 18.E.3.a chan 9 Hi 8.19E-6 1. 20E-4 18.E.3 .b chan 10 Al 5.73E-6 5. 8E-6 18 .E.4 .a chan 9 Hi 1. 31E-4 6.38E-4 18.E.4.b chan 10 Al 6.56E-5 3. 19E-4
- 2) Ensure step E.8 filled out, and E.9 is N/A'd on copy given to examinee.
4 S-41 (7/2/01)
ZD73EXAM
BwOP WX-501T1 Revision 19 Continuous Use LIQUID RELEASE TANK OWX01T RELEASE FORM Release Number L -
A. OPERATING DEPARTMENT RESPION OPERATOR "ILMLRADWATE besired level is 85% to 90% forNReleaseOTE.
however, a Release Package may be Package initiaton; n ot initiated b e r un w l i s IT l eveOWXO anytime 7-'0 %.
'lev el is > 50%. T he m ixe r s ho uld Consideration should be given future water management whenR Ini needs 2*1.VERIFY 0WX01 TiRatingwith level < 85%.
a package T is Recirculating per BwOP WX-171.
Tank Recirculation Started 41g".02215 4-2. RECORD OWXO1T Tank Level.
OWXO IT Tank Level _4%
-~-3. COMPLETE the entries in the Liquid Release Log in the RWCR.
If a release is in progress for tank NOTE OWX26T, Step A.4., it may be marked N/IAI. It is checked again in Section D.
_4. If 0PR01 J is hM required for sampling of 0WX26T, VERIFY that the 0PR01 J return is lined up to OWXO1T by performing the following valve lineup:
- a. VERIFY/OPEN "NO EPN", OPROIJ return to OWXOIT.
- b. VERIFY/CLOSE "NO EPN", OPROIJ return to OWX26T.
_L5. RECORD the Release Number from the Uquid Release Log in the space provided on page 1.
1
BwOP WX-501T1 Revision 19 Continuous Use The minimum mixing time required NOTE J ,5 *t~, if recarculating with the mixer for anONaccurate or 60 minuIlg.,
sample isif recirculating with the mixer OFF. After meeting time requirements, Chemistry can be called for a sample.
A_1 L6. WHEN the minimum rixing time requirements have been satisfied, Cheipstry that a Release Package NOTIFY in progress requires 0WX01T sampling.
If more than 25% of the volumeNOTE In the was drained or processed out of one Release Tank is water that or more systems to support Refueling or Forced Outage Ca*ivities, it is Outage Watero.
Is the water in this tank considered to be outage water?
[/YES "13 NO
'0'N
___8. Is 0WX01T level greater than 80%
(From Step A.2.)?
"* YES (GO TO STEP A.9.)
03 NO (MARK STEP A.9. -N/A-.)
If more than 55 gallons of caustic NOTE Tank Chemical Addition area (426'has accumulated at the Release by IA FW Pp), a caustic add should be performed unless directed otherwise by the Shift Supervisor based on release proriy.
-- 9. Is it desired to add caustic to 0WX01T?
0 YES X NO
( 10. VERIFY/DELIVER this release package to the non-outage Unit Supervisor.
2
BwOP WX-501T1 Revision 19 inuous use B. OERATIG PONSIBILIY - UNIT Su,.,Pymno Kankakee River Flow rate is NOTE forornormally teUA CORPS OF ENGINEERS, obtained via the internet site (from t appropriate Unit WILMINGTON Supervisor). If data is unavailable DATA RECORD most recent data from the Unit Supervisor turnover.
t ...... "'-
Stream-Flow: 7.80 CFS
,u current (within the last - hrs.) Kankakee River flow data:
at Date: 4-_9zo L o at..Time: "
RECORD the START AFTER Otim from BwOP WX-501T2, a 2. for the flow rate recorded Release Time Table, in Step .1.
Release canstartat.er' /100 TSS analysis is required NOTE on &L tanks released the sampling week, that on the first ddy of releases are performed.
analysis tank of the addmonth 4-5 hou* .t Oil requires . ,*anda Grease The first reease L m s .a ay s These analysis. h s sam analysis calculatis-, smleple aoi crs to the Processing time.
require All second verification chemistry Chem Tech Available, (if there is only one the verification Occurs the release Package can Process following shiift). A hours if there are two Chem through Chemnistry in as little as three Techs. there are no higher caustic add is required, priorities, no and OPROIJ Is operable.
3e Mt Ie feIA s t
..,- ,, canE,be release th*-e accommodated expected time Of release so that both bi biocide c treatment r
and the considering: m th
- CW Biocide treatment requires associated Unit CW blowdown isolated.
- At least 8000 GPM CW blowdown flow is required for the Liquid release.
RECORD the Kankakee River flow rate obtained
- 4. in step B. 1 in the Unit f- Supervisor Turnover.
3
BwOP WX-501T1 Revision 19 Continuous Use B. 5. AAR OBwOS RETS 2.1-la in effect for:
0 ORE-PR001 13 YES , NO VERIFICATION 14,,)
S0 ORE-PR010 0 YES NO VERIFICATION NOTE Prior to forwarding this Release Package to the Chemistry Department, Step E.1. and E.2. may be performed if operating conditions permit.
6.
/at Date e q4T Time NOTIFY the RADWASTE OPERATOR that his release package is ready for prompt delivery to Chemistry.
t 7.
4
BwOP WX-501T1 Revision 19 Continuous Use C. CHEMISTRY DEPARTMENT RESPONSIBILITY I NOTE JM0% level for theOWXOIT release tank is 32. gallons.
IfORE-PROO1 Is inoperable under NOTE AAR analyses other than isotopic required in OBwOS RETS 2.1-la, this package, i.e., Tritium, Boron, 0 & G (if required), and TSS (if required) numbers reported on one of two samples must be run and the that meet the 30%
acceptance criteria.
I. To verify a request has been made to add
-verify. yes applies to all statements specifiedcaustic to OWXO1 T Release Tank, in step A.8 and A.9.
o All statements are yes, a chemical addition has been requested, proceed to step C.2.
Not all statements apply. A chemical addition will not be performed, proceed to step C.3.
- 2. Caustic addition to OWXOIT.
- a. Sample and analyze OWXOIT for boron concentration.
Sampled by A)i- Time/Date £7 Results A/r ppm (Record boron value in step C.9).
- b. Submit a chemical addition using BwCP 340-1T4 for caustic to OWXOIT based on the following chart.
5
BwOP WX-501T1 Revision 19 Continuous Use C. 2. c. Chemical Addlti gallons caustic submitted by m*e/Date uro . Proceed to step C.2.d.
OPSSu OR rvisor notified that noca cisto be added based on boron concen OPS Supervisor no TimeDate by Chem Tech Proceed to step C.3.
- d. After receiving notification that the caustic addi on to 0WX01T is complete proceed to step C.3.
Time/Date notified that add was completed
- 3. Sampling the R eETffluent, a nk After obtaining a sample of the Release Tank, Section C (Excluding sections C.1 and C.2). the analysis listed in can be performed in any order rnesakry to perform the analysis fashion. It is not necessary to complete one in a safe and timely analysis before starting another. The sequence of performing the discretion of individual performing the tasks. analysis Is left to the 1st Set 2nd Set (If Required) 1st Sample 2nd Sample 1st Sample 2nd Sample If R uired if R uired) 3mpled by imple Time O
- a. One liter in a poly bottle for isotopic analysis (per BwCP 210-11), tritium analysis (per BwCP 220-2), boron analysis (per BwCP 103-10) and 250 ml for the monthly save" (monthly composites).
- b. For the first release package of the month, analyze for Oil and Grease analysis as directed per BwCP 323-18.
6
BwOP WX-501T1 Revision 19 Continuous Use NOTE Additional release packages sampled on the same day as those analyzed in Step C.3.c. will require TSS samples also.
C. 3. c. For theday of the first release package of the week, obtain asample for Total Suspended Solids (TSS) analysis for ALL releases as directed per BwCP 323-18.
- 4. ISOTOPIC SAMPLING CHECK
- a. If Radwaste Effluent Process Monitor, ORE-PR001 is operab per AAR OBwOS RETS 2.1-1a (see Step B.5.) then N/A Step C.5.
- b. If Radwast 9 Effluent Process Monitor.
ORE-PROOI 11 D&S opera per AAR 0BwdS F&S 2 '.1-l1 (see Step B.5.) then perform Step C.5.
If an Isotopic Voeication S... . is..to.Oe NO TE performed then an independent , .,, .o sample of sufficient volume for.an Isotopic must be taken by an i.ndependent qualified individual. Fill .
in Table on page 6.
- 5. ISOTOPIC RIFICATION
- a. VERIFY that Cobalt 58 (Co-58) activifies, Mean Decay Corrected Table, are within obtained from the Weighted NQ% of each other by performing the following calculation:
A/B < 1.30 Where:
A = The Larger Co-58 activity, piCi/g =
B = The Smaller Co-58 activity, pCi/g =
A/B =
If the activities are within 30% of each other, N/A Steps C.5.b. through C.5.f. and proceed to Step C.6.
7
BwOP WX-501T1 Revision 19 l*Pt C Continuous Use
- b. If the activities were not within 2Q% of each other, perform the following:
- 2) INFORM OPS Supervision.
- 3) OBTAIN another set Of INDEPENDENT samples.
- 4) PERFORM an isotopic analysis on each of the second set of samples.
- 5) VERIFY that Cobalt 58 (Co-58) activities, obtained from the Weighted Mean Decay Corrected Table, are within 30% of each other by perforriing the following calculation:
Where:
A =.The, Larger Co-58 activity, p.P-ig =
B = The Smaller Co-58 activity, A/B= Ci/g =_
- c. A second INDEPENDENT set of samples has been obtained, analyzed and the Co-58 activities verified to be within 2Q% of each other.
o YES, PROCEED to Step C.6.
o NO, INFORM OPS Supervision and Chemistry Supervision immediately. Save other analysis results, i.e.,
boron, 0 & G (if required) and TSS (if required) Tritium, obtained on the second set of samples.
Signature Date 8
BwOP WX-501T1 Revision 19 Continuous Use Chemistry and OPS SupervisionNOTE will attempt mismatch. Further INDEPENDENT samplingto resolve the activity and isotopic analyses may bue necessary. Radiation Protection Supervision may need to J bDe consulted to re-evaluate the 2% acceptance criteria.
- 5. d. Radiation Protection has waived 2Q%
acceptance criteria.
Rad. Protection Supervisor Date Time OPS Supervisor Date lime
- e. If Radiation Protection waives the IQ%
acceptance criteria, report analys*li results for Tritium, boron, 0 & G (if required) and TSS (if required) obtained on the second set of samples.
- f. if Rad'al.on Protection'does not waive the discard analysis results fo# Tritlum, boron, 2Q% acceptance criteria, 0 & G (if required) and TSS (if required) obtained on the second set of samples.
that this package is terminated and return Notify OPS Supervisor to him. Chemistry Supervision will begin an Investigation to determine the difference.
- 6. Radionuclide Analysis Performed (Isotopic report(s) attached)
M__7. ANALYZE sample for tritium per BwCP 220-2, and RECORD the completed BwCP 220-2T1. results from the PARAMETER FRQUEN.CY LIMIT RESULTS Tritium I Each Batch None31 C e8. Composite sample drawn, labeled with sample time, date and assigned release number and placed in designated sample storage area.
- 9. ANALYZE sample for boron concentration, if not previously obtained in step C.2, per BwCP 103-10 and RECORD the results below.
PARAMETER FREQUENCY POST DILUTION TANK DISCHARGE LIMIT CONCENTRATION Boron Each Batch 5 1 ppm 2I L pPm 9
BwOP WX-501T1 "Revision 19 Continuous Use
- 10. Maximum Discharge Rate based on Water Quality Chemical Analysis PERFORM the following calculation for each analysis:
A x B = MAXIMUM DISCHARGE RATE C (gpm)
"A= Kankakee River Flowrate = 91.392 gpm.
B = Parmeter Limit = I ppm C = Tank Concentrtion (from Stop C.9.)
Maximum Discharge Rate S" / 1 gpm (not to exceed §0 gpm)
AJl re*de NPDES LIMITS must be satisfied in the release I
pr:oror a release. . .
tank *,
- "NOTE N11- ANALYZE sample as required by the NPDES Permyt for Total Susened Solids per.CY- 13.-914O
.- and Oil and Grease per BwCP 100-1O: RECORD results from the completed appropriate T-sheets the- .
bel6w arW on BwCP 323-18T1.
NWA this Step If NPDES sampling has been satisfied.
PARAMETER FREQUENCY LIMIT RESULTS otal Sus eed Solids Per Current NPDES'Permnit ppm ppmm30 II and Grease _er Current NPDES Permit Is 20 ppm ppm 10
BwOP WX-501T1 Revision 19 Continuous Use C. 12. Is the Release Tank within all specified NPDES limits as determined in step C.11?
ff YES a. The release tank is approved for Chemical Release.
- b. Perform Step C. 13., then forward this procedure to the Health Physics Department or back to the Operating Department for Step E. 1.
o NO a. IMMEDIATELY NOTIFY the OPS Supervisor OPS Supervisor notified:
/ I (Print Name) Date Time
- b. RETURN'this procedure to Health Physics for release cancellation.
- 13. Chemistry Department: I have reviewed Part C and have verified It is accurate
- '*rldstsry(Deprtment Date Time
_ _ AI4o _ 5 Verification Date Time ZP4 14. PROMPTLY DELIVER this release package to Health Physics for processing (ENSURE receipt is acknowledged).
11
BwOP WX-501T1 Revision 19 Continuous Use D. HEALTH PHYSICS DEPARTMENT RESPONSIBILITy RADIONUCLIDE ANALYSIS IfORE-PROOl (Liquid RadwasteNOTE Release two release tank samples must be obtainedMonitor) is out-of-seryice and analyzed. For all
!ql8spalculations th jyff concewntralone (from the two analyses) SHALL be used. Ifan of each only one of the two analyses, then use that value isotope appears on for the isotope.
Obtain the following and attach to this release form:
- a. I*.otpic(s) for the tank to be released..
._&2. CALL the Unit Supervisor and VERIFY that there are no .Liquid Release In Progress" placards on panel 0PM01J. *,* -Z CT, NOTE and AAR 0BwOS RETS 2.1-1a has been initiated.
- 3. Call the OPS Supervisor for the following: *i'O/,
- a. Verify no OWX026T release package (BwOP WX-526T1) is in progress past Step D.2 and prior to Step 1.1.
- b. Verify that the backflush of the ORE-PRO01 was completed more than 2Q minutes ago.
- c. Verify that the OPRO1J return is lined up to 0WX01T by either
- 1) Checking Placard on Radwaste Control Panel OR
- 2) Performing the following valve lineup:
a) OPEN "No EPN", 0PR01J return to 0WX01T.
b) CLOSE "No EPN", 0PR01J return to OWX26T.
12
BwOP WX-501T1 Revision 19 Continuous Use D..#4. Call the NSO and Request the 3 most recent
- 1. minute average readings from RM-11 for the ORE-PR001 (OPSI01). ,.' - $-"
Date: /-oe- Time: /530
- 1 ; ACi/rmi
- 2 s gC/rl/m
- 5. Recdrd the naximum background for ORE-PR001
ý6ained from 3 average readings in Step D.4. above = I,. r MCi/r/m Ifa computerized release programNOTE is available, printout to this form and indicate "see attached" you may attach the spaces In Ste D.6.a: b."l:' Ifno quantifiable in the calculation he radlonuclide analysis, write "NQPF" in peaks are found in the Table in Step D.6.a.
Actual release data will be completed in Section I.
-&'6. RADIOACTIVE REL_..E RATE DETERMINATION:
- a. To ensure compliance of the planned release BwRP 6110-12, COMPLETE the table below. with IOCFR20 limits and If an isotope is not present, you may leave the space blank.
13
BwOP WX-501T1 Revision 19 Continuous Use D. 6. a.
NOTE DWC values are listed in 10CFR20, Appendix B Table 2, Column 2.
For Tech Spec Unit take ten times the DWC value for each isotope listed for calumn 3. (i.e. the DWC value for Co-58 is 2E-5 Ci/rMl.
The value listed in column 3 below ould be 2E-4 pCi/m.l.) The Tech Spec U,,mt for noble gas isotopes is 2E-4 phiC/hlper OCM Radioactive Effluent Technical Standard 12.3.
1 A.
- 1 2 #3 45 aeiopeT* Tech Spec Umnt (cIACIn) Completed unti Step D.6-a-J 2Unrestricted Area DC Fraclon
.54 N.0 57 . -,
56 9iF ..
Sum of column #4 DOES indude Tritium 14
BwOP WX-501T1 Revision 19 Continuous Use D. 6. b. VERIFY that the total tank curies excluding noble gas and tritium, are less than the administrative limit. If exceeded, receive permission from the OPS Supervisor to release the tank.
/I OPS Supervisor Contacted (print) or N/A Date Time "c.' *irculating Water Blowdown. :
- GPM.
- d. RADOACTIVE RELEASE RATE Radioactive Release Rate ECirculating Water Blowdown Rate (8,000gpm)]/
Total of Column 4 2
= LI-, [*e GPM Date: - Time: /S",1£
- (not to exceed gpm) q L
- e. MAXIMUM RELEASE RATE DETERMINATION:
CHOOSE the most imiting (smallest) release rate, either the Chemrstry release rate from Step C.10 or the Radioactive Release Rate in Step D.6.d. above.
MAXIMUM RELEASE RATE 3/1 GPM
- f. Calculate the minimum release duration using formula below.
Minimum Release = ITank Volume (Gal) - 3300] =
Min Duration Max. Release Rate (GPM)
- g. UNRESTRICTED AREA DWC FRACTION (Verification):
- 1) COMPLETE column #5 of Step D.6.a. using the following equation on a radionuclide basis:
DWC Fraction= Analyzed Tank Activity (pCi/mI) x Max. Release Rate (gpm) T S
[Max. Release Rate (gpm) + Circ Water Blowdown Rate (8,000 (gm)J
- 2) VERIFY the sum of column #5 is less than 0.5.
If not, NOTIFY the OPS Supervisor and CANCEL this release form.
15
BwOP WX-501T1 Revision 19 Continuous Use NOTE Step D.7. is not required if ORE-PR001 is inoperable and AAR OBwOS RETS 2.1-1a has been initiated.
D&,7. RADWASTE EFFLUENT MONITOR. SETPOINT:
- a. DETERMINE the AJert Alarm and High Alarm sstpoints Radwaste Effluent for the Uqui Monitor (ORE-PR001) using the following equation:
ORE-PR001 maximum background from Step D.5.
(&f(vt-., CI/mi Calculated ORE-PR001 setpoint = [(Total Analyzed Tank activity*) x 1.5]
+ (Max. 0.R-PR001 6kg).
suni'aof 6&oumn 2 Step D.6.a.
RECORD the calculated ORE-PROO setpoint li-. pci/r ..
COPARE the calculýted 0RE-PR001 setpoint to each of the current ORE-PR001 monitor setpoints. These setpoints are:
131E-4 MCi/rn for the HIGH setpoint 6.56E-5 MCi/rnl for the ALERT setpolnt If the calculated value is less than the current monitor setpoint, RECORD the current monitor setpoint as the Release setpoint.
value is greater than the current monitor setpoint, If the calculated RECORD the calculated value as the Release setpoint.
- b. RECORD ORE-PRO01 Monitor Liquid Release setpoints:
4A1Chan Item 9 (HIGH Alarm Setpoint) I A,,/%j1__
Ci/ml LChan Item 10 (ALERT Alarm Setpoint) da'3M-'- -Ci/mrni 16
BwOP WX-501T1 Revision 19 Continuous Use NOTE Step D.8. is not required if ORE-PR010 is inoperable and AAR OBWOS RETS 2.1-1a has been initiated.
D. 8. STATION BLOWDOWN MONITOR SETPOINT:
a, 7 *WTiERMINE the ALERT Alarm and HIGH Slowdown Process Monitor ORE-PR010 AaII* sepok for the Stition using the following equation:
ORE-PR010 ORE-PR010.25x Total Setpin current Circ. Water Blowdown Rate of A Max RaseRge readpg gpm + Max Release Rate
- Sum of column #2, Step D.6.a.
ORE-PR010 current reading. _ *,7j ,iCi/rrI Calculated 0RE-PR010 setpoiro
,-9,aL-(jf ICn*Cit COMPARE the calculated ORE-PR010 Setpoint to each of the current monitor setpolnts. These setpoints are:
8.19E-6 ACi/mi for the HIGH setpoint 5.73E-6 ACi/rn for the ALERT setpolnt If the calculated value is less than the current monitor setpoint, RECORD the current monitor setpolnt as the Release setpoint. If the calculated value is greater than the current monitor setpoint, RECORD the calculated value as the Release setpoint.
- b. RECORD ORE-PR010 Monitor Uquid Release setpoints:
"41. Chan Item 9 (HIGH Alarm Setpoint)
A MCi/rmI Chan Item 10 (ALERT Alarm Setpoint)
- Ci/rnl A
17
BwOP WX-501T1 Revision 19 Continuous Use D. 9. APPROVAL FOR RADIOLOGICAL RELEASE:
Radiation Protection: I have reviewed Part D and have verified it is accurate and complete.
Radiation, ro° o*n Date Time "I,'**-NOTE .'
Verification is required for Step D.9.
if ORE-PR001 is inoperable and MAR OBwOS RETS 2.1-Aa has been Initiated.
RP or Chem: I have verified that Part D Is accurate and complete.
VERIFICATION Date: Time: ......
- 10. Forward Release Package to the OPS Supervisor, or Contact OPS Supervisor for irtf-nicuons to fowa*d this package.
18
BwOP WX-501T1 Revision 19 Continuous Use E. OPERATING DEPARTMENT RESPONSIBILIlY NOTE iAChec Source Check. is a verification of Detector Response. Even Dt cItor responseus immedlately evident when~ a -Hot-f ifsi Release uto OPROU.:OOCMRET2-1.-
'u"rce Check. Ifa Check SoWm -mlg a Pruset. It 1s cated by the programTest fls *irHlhN Ac* is' S" te .Check SiArce Test, the Actit fLs:tIjn 4rfpROjj. 'Topast has -to s~ta , or. be hise,,,
and repeated attet may have to be perfokmed until successful.
A-NOTE Step E.1. Is not required IfORE-PR001 is knpeabl and AR OBwOS RETS 2.1-la has been Initiated.
1.- Performn0BWQ6RET$ 2.1.8-1. -unit Commonh Pf6-Relee Source Check of Uquld Effluent Monitor OPROIJ."
Time:'"*'f1
- Date: .j -CE-
- 2. Control ROOM Supervisor I have verified that either the OBwOS RETS 2.1.13-1 Acceptance Criteria has been met, or ORE-PRO01 is inoperable.
nuRoom pupeJ(sor Date Generally. a low flow release rateNOTE should be considered as <=30 gp.m Contact OPS Supervisor for determn*ation flow path to use based on current conditions, of which release equipment availability, etc.
'__3. CONTACT OPS Supervisor for release flow rate path.
_4. CIRCLE release flow rate Path.(_*-MHigh Flow.
19
BwOP WX-501TI Revision 19 Continuous Use IwONOTE I Step E.5. is not required if ORE-PR010 is inoperable I 08WOS RETS 2.1-1a has been initiated.
and MR E. 5. OB.TAN and RECORD he values of the olowing CHAO ITEMS for the,
. RE -',4)I, (OPS110) from Its CHAN ITEM Display oi* lih RM.11
.(ODPR*8S Grid 1 key, key In 110, DEPRESSSELftY.nd Cbnsole.
ihn DEPRESS CHAN ITEMS key).
Sa. Chan Iem9 (HIGH Alarm Setpolint) '(9t'*-,uml
- b. Chan Item 10 (ALERT Alarm SetpoInt)"*'S*'*,*rn-i I
6.
NOTE Step E.6. Is not required IfORE-PR001 OBwO RETS;ZI1a has been Intated. inoperable and AAR OBTAIN and RECORD the values of is the following CHAN ITEMS for the ORE-PROOI (OPSI01) from its CHAN ITEM (DEPRESS GRID 1 key, key in 101, DEPRESS display on the RM-11 Console.
SEL key and then DEPRESS CHAN ITEMS key).
- a. Chan Item 9 (HIGH Alarm Setpoint) 1.JE-26Ci/rrl
- b. Chan Item 10 (ALERT Alarm Setpoint) 1-.;b t-ogmirnl 20
BwOP WX-501T1 Revision 19 Continuous Use E. 7. VERIFY OBwOSR 0.1-0 daily channel check is complete on:
NOTE Step E.7.a. is not required if ORE-PROO1 is inoperable and AAR OBwOS RETS 2 .1-1a has been initiated.
Red Monitor ORE-PR001: Lquid Radwuste Effluent. .
NOTE Step E.7.b. Is not required if ORE-PR010 is Inoperable and AAR 0BwOS RETS 2.1-1a has been initiated.
- b. Red Monitor ORE-PR010: Station Blowdown.
Step E.7.d:. is ndt'requihi-ed f 0'UR-CW032 NOTE Is Inoperable and AAR *..
OBwOS RETS 2 .1-1a has been initiated.
- c. Station Blowdown Une Monitor Loop OUR-CW032.
21
BwOP WX-501T1 Revision 19 Continuous Use NOTE Steps E.8. and E.9. are not required if ORE-PR001 is inoperable and AAR 0BwOS RETS 2 .1-1a has been initiated.
NOTE a release through the low flow ratO path and mar step E.9N/A. t(a OMLETE Step E.8 high flow rate release, -PROCE* M to Step E.9 and mark step E.8 N/A.
Ifthe 0PR01J is in High Aarrat NOTE this high backgrouj , it will be rnecssary point in t procedure due to setpoint to a value higher than the fo reset the HIGH alarm background. This will allow the OAOV-WX896 to oel to test the Interlock function. Otherise, FE.ý8.f. is not required. Step Upon receipt of a high radiationNOTE signal at OPROIJ, the Release Tank Discharge Valves, 0WX353 and 0WX896 will remain dosed until high radiation signal the seal-in is reset at OPLOIJ.
E. 8. VERIFY valve OAOV-WX896, Release Tank Disch Isolation Valve, automatically N/A doses on high radiation by PERFORMING the following Steps:
- a. VERIFY sufficient blowdown flow is established.
N/A b. VERIFY/CLOSE OAOV-WX897, Flow Control Radwaste Effluent V/A Discharge Valve.
C. VERIFY/CLOSE OAOV-WX890, Release Tk Pp OWX53P Dsch Isol.
AA d. VERIFY/OPEN OAOV-WX889, Release Tk Pp 0WX01P Dsch Isol.
A _ e. VERIFY/START OWX01P, Release Tank Pump.
22
BwOP WX-501T1 Revision 19 Continuous Use E 8 f IF the OPRO1J is in HIGH alarm, CHANGE the HIGH alarm setpoint to a value higher than background. This will DISCHARGE HEADER RADIATION HIGH allow the RELEASE TANK alarm (Window 77A09 on OPLOIJ) to be reset and the OAOV-WX896 valve to be opened after its seal-n has been reset. This can be accomplished as follows:
m CAUTION
" Some actions possible In the Supervisor seftoms detrimental effects on system Mode may operatn.=, have Theetore use caution when in this mode leave the RM-1 I console unattended when and'd not it is in this mode.
- 1) PLACE the RM-1I Console in SUPERVISOR MODE.
- 2) SELECTt IGHalarmsetpod nnel Item 9) to be. chnged on the ORE-PR001 (OPSIOJU 'EMS display by KEYING In 0 and DEPRESSING (Following this CHAN ITEM 9 should be displa li~Fe characters.)
3)" EN ' larm setpolnt USING The format XYZ +
AB (1.e. a VB~~S1 E- 10 would be entered as 376-10)
EN~ key. The new value will be displayed and DEPRESS the after a short delay.
- g. VERIFY/CLEAR RELEASE TANK DISCHARGE HEADER RADIATION HIGH Annunciator (Window 77A09 on OPLOIJ).
Upon receipt of a high radiationNOTEsignal at OPRO1J, the Release Tank Discharge Valves, 0WX353 and 0WX896 will remain dosed until the high radiation signal seal-in Is reset at OPL01 J.
- h. OPEN OAOV-WX896, Release Tank Disch Isolation Valve.
23
BwOP WX-501T1 Revision 19 Continuous Use E. 8. i. AUTO CLOSE valve OAOV-WX896, Release Tank Disch Isolation Valve, by LOWERING the Liquid Radwaste Effluent monitor ORE-PR001 HIGH alarm setpoint to a value below the current activity as follows:
- 1) PLACE the RM-11 Console in SUPERVISOR MODE.
- 2) SELECT the HIGH alarm setpoint (channel item 9) to be changed on the ORE-PRO01 (OPS101) CHAN ITEMS display
.* 9and DEPRESSING the SEL key. (Following' tis CHAN bWKEYING in, ITM "
should be displayed In reverse characters.)
- 3) RECORD the current activity reading.
- 4) ENTER a new HIGH alarm setpoint below the current activity value (from the upper right comer of the display) USING the format XYZ + AB'for XYZ E + AB (i.e. a value of 3.78E-10 would be entered as 376-10).
- 5) "RECORDutw~,e HIGH alarm selpolnt #Wat was entered. .3 .3.
(hainnel item 9)_____
- 6) DEPRESS the ENTER
- 7) the RM-11 console.
- j. VERIFY Release Tank Disch Isolation Valve, Auto Closes.
- k. VERIFY RELEASE TANK DISCHARGE HEADER RADIATION alarm (Window 77A09 at OPLOIJ) annunciates at OPLOIJ HIGH and ACKNOWLEDGE.
I. PLACE key locked switch for OAOV-WX896, Release Tank Disch Isolation Valve, in CLOSE.
24
BwOP WX-501T1 Revision 19 Continuous Use CAUTION V~~ WIOUS*deiiementa. effects Some aactions possible on Supervsor system operation.,
in the heeforeuse caution when in this mode Mode may have WW..
leave the RM-1 1 console unattended and do not when It Is In this, Mode.
E 8. m. VERIFY/ADJUST the ALERT Alarm and HIGH Alarm setpoints for ORE-PR... (OPS1OI) to the values specified by Health Physics in Step D.7.b. USING the instructions that follow.
VERIFICATION
- 1) PLACE the RM-1 I Console in SUPERVISOR MODE.
- 2) 3ELfCT thq ALERT alam mitnt onthet1 , (channel ftemi0) to be WS101)
Nn CHAN ITEMS display by KEYINGSG the SEL key. (Following this
" ;k "dubdie displayed in reverse characters.)
f ABTER the new ALERT alarm setpoint.USING. the format XYZ AB (i.e. a value of 3.76E-10 would
- DEPRESS the ENTER key. The be entered as 376-10) and new value will be displayed after a short delay.
- 4) SELECT the HIGH alarm setpoint (channel item 9) to be changed on the ORE-PR001 (OPSI01) CHAN 9 and DEPRESSING the SEL key. ITEMS display by KEYING in (Following this CH-^AN ITEM 9 should be displayed in reverse characters.)
- 5) ENTER the new HIGH alarm setpoint USING the format XYZ +/- AB (i.e. a value of 3.76E-10 would be DEPRESS the ENTER key. The entered as 376-10) and new value will be displayed after a short delay.
- n. VERIFY/CLEAR RELEASE TANK DISCHARGE HEADER RADIATION HIGH annunciator (Window 77A09 at OPLO0J).
25
BwOP WX-501T1 Continuous19 Use Revision If the OPROIJ is in High Alarm NOTE at this point in the procedure due to to~h background, t W*ll be sVtPoint to a value higher thannecessary to resSt.IheHIGH the background: This willalarm allow the "QAOV-WX353 to open to test the interlock Rxtgi t-,94 is not required. OgvhevwAs, Step
.E..
se, p E. 9. VERIFY valve 0WX353, Release Tank Disch doses on high radiation by PERFORMING Isolation Valve, automatically the following Steps for a release through the high flow rate path:
- a. VERIFY sufficient blowdown flow is established.
- b. CLOSE oAOV-WX302. Flow Control Radwaste Effluent Discharge Valve.'
- c. VERIFYICLOSE 0AOV-WX8gO Release Tk pPOWX53p Dsch 1sol.
- d. VERIFYIOPEN 0AOVNXW889j Release Tk Pp 0WX01P Dsch Isol.
- e. VERIFY/START OWX01P, Release Tank Pump.
26
BWOP WX-501T1 Revision 19 Continuous Use som atinsCAUTION SeriousSom acios pssbleinthe Supervisor Mode detrimental effects on system operation..may have Therefore use caution when inthis mode and do not "e the RM-1 I cnsole unattsnds Mien It Is 'I this E IF the OPRO. J is in HIGH alarm, CHANGE the HIGH value higher hnm background. alarm setpoint to a This DISCHARGE HEADER RADIATION will allow the RELEASE TANK OPLO1J) to be reset, and the HIGH alarm (Window 77A09 OAOV-WX33 valve to be on seal0n has been mreet This opened after its can be accomplished as follows OPROIJ is not in alrm): (N/A if
- 1) PLACE the RM-1I Console in Supervisor Mode.
- 2) SELECT the HIGH alarm setpoint 06on theORE-PRO0 (OPS,,) (channel item 9) to C.,N IrEMS dnlay be changed 9 and bEPRES.IGthe SEL by KEYING in key. (Following this CHAN should be displayed In reverse ITEM 9 characters.)
- 3) ENTER a HIGH alarm value of 3.76E-10 Wouldsetpoint USING the fomilat XyZ +/- AB (i.e.
be entered as 376-10) and a ENTER key. The new value DEPRESS the will be displayed after a short delay.
"g- VERIFY/CLEAR RELEASE TANK DISCHARGE HEADER HIGH Annunciator (Window RADIATION 77A09 on OPLO1J).
Upon receipt of high radiation NOTE signal at OPROIJ, the Release Discharge Valves, 0WX353 and 0WX896 will remain closed Tank high radiation signal seal-in until the Is reset at OPLOIJ.
"h. OPEN OAOV-WX353, Release operate the OAOV-WX353 Tank Disch Isolation valve conbno switch must Valve.
be (The key to OPS Supervisor or Shift Manager.) obtained from the 27
BWOP WX-501T1 Revision 19 Continuous Use E. 9. i. AUTO CLOSE valve OAOV-WX353, Release Tank Disch Isolation Valve, by LOWERING the Liquid Radwaste Effluent monitor ORE-PR001 HIGH alarm setpoint to a value below the current activity as follows:
PLACE the RM-11 Console in SUPERVISOR MODE.
,2Y SELECT the HIGH alarm selpoint (channel item 9) to be changed on the ORE-PR001 (OPS101) CHAN ITEMS 9 and DEPRESSING the SEL key- (FolloWngq display by KEYING in iM CHAN ITEM 9 should be displayed in reverse characters.)
- 3) RECORD the current activity reading
- 7. * -0
- 4) ENTER a new HIGH alarm setpoint below the current activity value (from the upper right comer of the display)
USING the format XYZ +/- AB for XYZ E eftered 9as 376- 10). +/- AB (i.e. a value of 3.76E-10 would be S' 5) RECORD theneww HIGH alarm, se"~~n ftht was entered.
- 6) DDEPRESS the ENT*R key.
- 7) ACKNOWLEDGE the alarm at the RM-1 I console.
VERIFY OAOV-WX353, Release Tank Disch Isolation Valve, Auto Closes.
- k. VERIFY RELEASE TANK DISCHARGE HEADER alarm annunciates at OPL01J and ACKNOWLEDGE. RADIATION HIGH
.. PLACE key locked switch for OAOV-WX353, Release Tank Disch Isolation Valve, in CLOSE.
28
BwOP WX-501T1 Revision 19 Continuous Use V ~CAUTION Some actions possible in the Supervsor Mode may have serious detrimental effects on system operation.
Therefore use caution when in this mode and do not leave the RM-1 1 consuje unattended when it Is in this mode.'
VERIFY/ADJUST the ALERT Alarm and HIGH Alarm setpoints
"'lf 9. M. ORE-PR001 (OPS101) to the values specified, by Health for Physics in Step D.7.b. USING the instructions that follow.
VERIFICATION
- 1) PLACE the RM-11 Console in SUPERVISOR MODE.
- 2) SELECT the ALERT alarm setplnt (channel item 10) to be changed on the oRE-PR001 (OPS101) CHAN ITEMSdlsplay KEYING lh 10 and DEPRESSING the SEL key.- (Following by CNAN ITEM 10 should be displayed in reverse characters.) this
- 3) ENTER the new ALERT alarm setpoint USING the format XYZ +
AB (i.e. a value of 3.76E-10 would be entered as 376-10)
DEPRESS the ENTER key. The new value will be and displayed after a short delay.
- 4) SELECT the HIGH alarm setpoint (channel item 9) to be changed on the ORE-PR001 CHAN ITEMS display by KEYING DEPRESSING the SEL key. (Following this CHAN in 9 and ITEM 9 should be displayed in reverse characters.)
- 5) ENTER the new HIGH alarm setpoint USING the format XYZ
- AB (i.e. a value of 3.76E-10 would be entered as 376-10) and DEPRESS the ENTER key. The new value will be displayed after a short delay.
I_1 n. VERIFY/CLEAR RELEASE TANK DISCHARGE HEADER HIGH annunciator (Window 77A09 at OPLO1J).
RADIATION 29
BwOP WX-501T1 Revision 19 Continuous Use NOTE Step E.10. is not required if ORE-PRO10 is inoperable and AAR OBwOS RETS 2.1-1a has been initiated or if ALERT ALARM & HIGH ALARM setpoints have not changed from Step D.8.b.
E,10. VERIFYIADJUST the ALERT and HIG *-..nt. ORE specified by Healh Physicsin Stie b. usng,
. instruetlois that follow.
- a. PLAC 1 Console asor in Su Mode.
- b. SEL T the ALERT alarm se nt (channel item 10) to be changed on Vh ORE-PRO10 (OPSI10) C ITEMS display by KEYING in 10 and DEPRESSING the SEL key. Followfng this CHAN ITEM 10 should be displayed in reverse.cha ..
- c. EN`'ER1he.new ALER A*montUSINGot fr ,XYZ* AS value.of3.76E-10 -beentered as 376-10) and DEPRESS the (L6. I.
ENTER key. The value will be displayed after a short delay.
- d. SELECTthe HI alarm setpoint (cha I tem 9) to be changed on the ORE-PRO10 ( S110) CHAN ITEMS spl DEPRESSIN the SEL key. (Foil by KEYING in 9 and g s CHAN ITEM 9 should be displayed I everse charact
- e. ENTER new HIGH alarm se nt SING the format XYZ
- AS (i.e. a value o .76E-10 would be ent as 376-10) and DEPRESS the ENTE key. The new value will displayed after a short delay.
- f. P E the RM-1 1 Console in the NORMAL MODE.
30
BwOP WX-501T1 Revision 19 Continuous Use E. 11. RECORD the following data in the space provided.
- a. Circulating Water Blowdown Rate
/* gpm (OUR-CW032 at PNL OPMO1J, or corrputer Poinlt F2400)
- b. VERIFY CW BLOWDOWN RATE It EQUAL TO' OR GREATER THAN 4-1~ gpm.
12..*, h, I ..
Control Room Supervisor Date rime 31
BwOP WX-501 T1 Revision 19 Continuous Use F. Shift Manager OR SRO RESPONSIBILITY
- 1. VERIFY that Steps B.6., C.13., D.9. and E.12. are signed.
NOTE Biocide treatment of CW requires isolation of CW blowdown. The expected time of release and release duration must be considered
- s. that both biocide treatment and tt~e release can be.,
accomrnmodated.
- 2. VERIFY that the actual Circulating Water Blowdown Rate is equal to or greater than 8,00 gpm (OUR-CW032 at PNL OPMO1J, or computer point F2400).
I Shift Manager or SRO Date
- 3. PLACE a placard stating "Liquid Release in Progress" at OPM01 J.
- 4. APPROVAL FOR RELEASE
/ I Shift Manager or SRO Date Time
- 5. COMMENTS 32
BwOP WX-501T1 Revision 19 Continuous Use G. OPERATING DEPARTMENT RESPONSIBILITY
- Discharging Release Tank OWX01T to Circulating Water Blowdown Line.
NOTE If during the release, Circ Water Blowdown flow (Computer point F2400) is reduced to <.Q,.
F gpm, terminate the release2. If during the release, Circ Water Blowdown flow is reduced.
(low flow.intedock setpoint), VERIFY the relopse to .<7.._. gpm is-terminated. If Circ Water Blowdown flow can be re-established gprn the release may be restarted at step G.2 provided that the following conditions are met:
- Shift Manager permission is obtained.
- All applicable Steps are re-initialed/re-verified as necessary.
- No additions have been made to the Release Tank.
- Release totalizers have not been reset and the original totalizer readings are used to calculate the gallons released.
NOTE If Station Blowdown Line Flow Monitor (CW-032) is inoperable,.
effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.
NOTE If this procedure is aborted before any effluent is released, perform Step G.27.a. through Step G.27.n. and realign the directed by the OPS Supervisor, then perform StepOPROIJ as G.28. and Step H. before exiting this procedure.
NOTE The purpose of the release window is to minimize the interaction with the City of Wilmington Water Department intake periods.
- 1. OPS Supervisor performs the following:
- a. RECORD the START AFTER time from step B.2.
and the START BEFORE time from BwOP WX-501T2, RELEASE TIME TABLE, using the River Flow Rate from step B.1. and the release duration from step D.6.f.:
Start After Start Before 33
BwOP WX-501 TI Revision 19 Continuous Use G. 1. b. VERIFY release will start within release start time window recorded in step G.1.a. If release cannot start within times recorded in step G.1.a. this step is N/A. Proceed to step G.l.c.
OPS Supervisor date Time To start release outside of release stirtftime
'step G.l.a. VERIFY Authorizafio'j Releasewindow recorded in Outside of Release Window,
'WOP WX-501T3, is completedand ietained withthis package.
OPS Supervisor Date Time Ifthis procedure must be exitedNOTEprior to its completion, the following temporary alteration must be restored per Step G.26.
prior to exit.
- 2. PERFORM the following if AAR OBwOS RETS 2.1-1a is in effect for ORE-PR001 (refer to Step B.5.):
- a. OBTAIN Shift Manager or designee permission to perform the following Temporary Electrical Alteration.
SM/DESIGNEE VERIFICATION SUPERVISOR VERIFICATION
- b. REMOVE Relay Block KI at OPRO1J (inside the AC Power Panel) to allow opening of 0WX896/353, Release Tank Disch Isolation Valve.
SUPERVISOR VERIFICATION
- c. LOCALLY, at OPRO0J, place 2 placards stating "K1 RELAY REMOVED FOR LIQUID RELEASE":
"* ONE on the AC Power Panel for OPRO0J and,
"* ONE on the Rad Detector Cabinet for OPRO1J.
34
BwOP WX-501T1 Revision 19 Continuous Use G. 3. RECORD the following data in the space provided.
- a. Tank Level Start %
(OLR-WX01 1 at PNL OPLO1J)
- b. VERIFY level in Step G.3.a. is +/-5% OF LEVEL RECORDED IN Step A.2 (Page:. 1), or receive Supervisor approval to continue.
- o. RESET the Batch Totalizer reading to.zero 6t'NL'OPL01Jfor flowpath being used. (This step may be marked the..
N/A if Batch Totalizer is inoperable.)
- d. RESET the Cumulative Totalizer reading to zero at PNL OPLO1J for the flowpath being used. (This step may be marked N/A if Cumulative Totalizer is inoperable.)
m cCAUTION Failure to record and use the correct maximum permissible release rate may result in violation NPDES and/or 10CFR20 release criteria. of
- e. Maximum Release Rate from Step D.6.e.
(page 15) GPM SUPERVISOR VERIFICATION
- 4. STOP OWX36M, Release Tank Mixer (if applicable)
NOTE Step G.5. is not applicable if Steps E.1.
and E.2. were not required.
- 5. VERIFY Steps E.1. and E.2. (page 19) have been completed within the previous 24 hrs (If NOT, RE-PERFORM Steps E.I. and E.2.).
NOTE Verification is required in Steps G.6. through G.13.
if ORE-PR001 is inoperable and AAR OBwOS RETS 2.1-1a has been initiated.
- 6. VERIFY/CLOSE OAOV-WX834, Release Tank Inlet Isolation Valve for Release Tank OWX01T.
SUPERVISOR VERIFICATION 35
BwOP WX-501T1 Revision 19 Continuous Use G 7. VERIFY/CLOSE 0AOV-WX01 7, Release Tank Recycle Valve (Release Tank Discharge to Turbine Building Equipment Drain Tank Isolation Valve).
SUPERVISOR VERIFICATION
- 8. VERIFY/CLOSE 0AOV-WX910, Release Tank Pump Disch Valve (Release Tank Discharge to Regeneration Waste Drain Tank.,
.. I&PERVSOR VERIFICATION
- 9. VERIFY/CLOSE 0AOV-WX302, Release Tank Discharge Control Valve/(High Flow Path).
SUPERVISOR VERIFICATION
- 10. VERIFY/CLOSE, OAOV-WX897, Release Tank Discharge Flow Control valve/(Low Flow Path).
SUPERVISOR VERIFICATION
- 11. VERIFY/OPEN OAOV-WX889, Release Tank Pump 0WX01 P Discharge Isolation Valve.
SUPERVISOR VERIFICATION NOTE For releases through the low flow rate path, < 130 GPM or as specified by OPS Supervisor, COMPLETE Step G.12 and mark step G.13 "N/A". For releases through the high flow rate path, mark Step G. 12 "N/A" and PROCEED to Step G. 13.
- 12. Low Flow Release, PERFORM the following:
- a. VERIFY Step E.8. (beginning on page 22) has been completed. (N/A if ORE-PRO01 is inoperable and AAR OBwOS RETS 2.1-1a has been initiated)
- b. OBTAIN the key for OAOV-WX896, Release Tank Outlet Valve.
36
BwOP WX-501T1 Revision 19 Continuous Use NOTE If Circ. Water Blowdown Flow Low and/or Release Tank Disch Header Radiation High alarms are lit, it may be necessary to reset the Rel. Tank Disch Header & Isolation Valves 0WX896 & 0WX353 by pressing their reset button prior to opening OAOV-WX896.
NOTE Upon receipt of a high radiation signal at 0PRO1J, the Release Tank Discharge Valves, 0WX353 and 0WX896 will remain dosed until the high radiation signal seal-in is reset OPL01J.
G 12. c. OPEN 0AOV-WX896, Release Tank Outlet Isolation Valve.
SUPERVISOR VERIFICATION
- d. VERIFY/CLOSE OAOV-WX015, Release Tank 0WX01T Pump Recirc Valve.
SUPERVISOR VERIFICATION
- e. SLOWLY OPEN OAOV-WX897, Release Tank Discharge Flow Control Valve,(Low Flow Path) with controller 0FK-WX630, maximum discharge flowrate of 50 GPM, or less TO OBTAIN a by Step D.6.e., for the first three (3) minutes of than 50 GPM if required the release by checking at least one of the following:
O Low Flow Totalizer increasing.
O Low Flow Recorder increasing.
o OWXO 1T Level Recorder decreasing.
o Computer Point (F0002) for release rate increasing.
SUPERVISOR VERIFICATION
- f. RECORD Release Start Time Date:
SUPERVISOR VERIFICATION 37
BwOP WX-501T1 Revision 19 Continuous Use G 12. g. SLOWLY OPEN OAOV-WX897, Release Tank Discharge Flow Control Valve, with controller OFK-WX630, To OBTAIN a release rate NOT to exceed the maximum release rate specified in Step G.3.e.
SUPERVISOR VERIFICATION
- 13. High Flow Release, PERFORM the following:
. . . ý~.
ý8. VERJFY Step E.9. (beginning on page,26) has been completed. '(N/A.if.,
ORE-PR001 is inoperable and AAR OBwOS ;
RETS 2.1-1a has been initiated.)
- b. OBTAIN the key for OAOV-WX353, Release Tank Outlet Valve.
NOTE If Circ. Water Blowdown Flow Low and/or Release Header Radiation High alarms are lit, it may Tank Disch be necessary to reset the Rel. Tank Disch Header & Isolation Valves 0WX896 & 0WX353 by pressing their reset button prior to opening OAOV-WX353.
NOTE Upon receipt of a high radiation signal at OPRO1J, the Release Tank Discharge Valves, 0WX353 and 0WX896 will remain closed until the high radiation signal seal-in is reset 0PL01J.
- c. OPEN OAOV-WX353, Release Tank Outlet Isolation Valve.
SUPERVISOR VERIFICATION
- d. VERIFY/CLOSE OAOV-WX015, Release Tank 0WX01T Pump Recirc.
Valve.
SUPERVISOR VERIFICATION 38
BwOP WX-501T1 Revision 19 Continuous Use G 13. e. SLOWLY OPEN OAOV-WX302, Release Tank Discharge Flow Control Valve, with controller 0FK-WX001, TO OBTAIN a maximum discharge flowrate of 50 GPM for the first three (3) minutes of the release by checking at least one of the following:
"o High Flow Totalizer increasing.
"O High Flow Recorder increasing.
.O 0WX01T Level Recorder decreasing.
o Computer Point (FOOO1) for release rate increasing.
SUPERVISOR VERIFICATION
- f. RECORD Release Start Time Date:
SUPERVISOR VERIFICATION
- g. SLOWLY OPEN OAOV-WX302, Release Tank Discharge Flow Control Valve, with controller 0FK-WX001, TO OBTAIN a release rate not to exceed the maximum release rate specified in step G.3.e.
SUPERVISOR VERIFICATION
- 14. RECORD the Release Rate -Gal/Min SUPERVISOR VERIFICATION (LESS THAN MAXIMUM RATE DETERMINED IN STEP G.3.e.)
- 15. VERIFY the following:
NOTE Step G. 15.a. is not required if Batch and Cumulative Totalizers are not operable. Gallons released shall be determined per note prior to Step G.20.e. if both totalizers are not operable.
- a. Batch Totalizer and/or Cumulative Totalizer readings increase. (It is acceptable, however, to observe no increase in the readings at low release rates).
39
BwOP WX-501T1 Revision 19 Continuous Use NOTE Step G.15.b. is not required if OFR-WX630-1 or OFR-WX630-2, as applicable, is inoperable and AAR OBwOS RETS 2.1. la has been identified.
G 15. b. PERFORM a Channel Check per OBwOSR 0.1-0 for OFR-WX630-1 or OFR-WX630-2, as applicable, by OBSERVING indication at OPLO1J.
NOTE Step G.15.c. is not required if OUR-CW032 is inoperable and AAR 0BwOS RETS 2.1-1a has been identified.
C. PERFORM a channel check per OBwOSR 0.1-0 for Flow Monitor by observing OUR-CW032, indicated the Station Blowdown on Panel OPM01.J, or computer point F2400.
- d. RECORD Station Blowdown Flowrate during release: _ gpm
- e. RECORD Station Blowdown Flowrate once per 24 Hr. on continuous release: gpm (N/A if not applicable)
- f. NOTIFY Control Room of release in progress.
- g. NOTIFY Shift Manager of release in progress.
40
BwOP WX-501 Ti Revision 19 Continuous Use G. 16. PERFORM the following rate checks. REFER to Attachment A as needed.
- a. For the high flow rate path check the flow rate using a tank level calculation over a 10 minute interval against computer point FOOO1 or Flow Recorder. PERFORM this check twice at the beginning of the release and again when < 50% level. RECORD-each flow rate obtained.
b.. For the low flow rate release path check the 0ow'rate using a tank level calculation* ver a 10 minute interval'against Ooht1uter point-FOOO2.or Flow Recorder. PERFORM this check twice. at4hdbeginning release. Providing the flow rates are consistent of the . '
and below the allowed release rate the release flow rate checks can be relaxed to once every 30 minutes. RECORD each flow rate obtained.
Where: At = Stop Time - Start TIME Al = Stop LEVEL - Start Level L2_9 = gallons per 1% tank level After each check of flowrate, VERIFY the flowrate is less than the maximum release rate specified in step D.6.e. and/or G.3.e, if not, IMMEDIATELY NOTIFY the OPS Supervisor.
41
BwOP WX-501T1 Revision 19 Continuous Use Attachment A Liquid Release Rate Chart
%Level % Time Change Change 5.00 10.00 15.00 20.00 25.00 30.00 35.00 40.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.50 32.90 16.45 10.97 8.23 1.00 6.58 5.48 4.70 4.11 65.80 32.90 21.9. 16.45 13.16 1.5& 10.97 9.40 8.23
-9'W70 49.35 32.90 24.68 "19.74 2.00 '16.45 " 14.10 12.34 131.60 65.80 43.87 32.90 26.32 2.50 t64.50 21.93 18.80 16.45 82.25 54.83 41.13 -.02.90 27.42 3.00 17,.40 98,7.0 23.50 20.56 65.80. 49.35 0 .4 32.0. 28.20 3.50 23030 115.15 24.68 76.77 57.58 460 38.8 32.90 4.00 Ift.20 131.60 87.73 65.80 -52.64 28.79 4.50 296.10 4117 38.60 32.90 148.05 98.70 74.03 5922 49.35 5.00 329.00 42.30 37.01 164.50 109.67 82.25 65.80 54.83 5.50 361-90 180.95 47.00 41.13 120.63 90.48 72.38 60.32 51.70 6.00 394.80 197.40 45.24 131.60 98.70 78.96 65.80 56.40 6.50 427.70 213.85 142.57 49.35 106.93 85.54 71.28 61.10 53.46 7.00 480.60 230.30 153.53 115.15 7.50 92.12 76.77 65.80 57.58 493.50 246.75 164.50 123.38 98.70 8.00 82.25 70.50 61.69 526.40 263.20 175.47 131.60 105.28 8.50 559.30 87.73 75.20 65.80 279.65 186.43 139.83 111.86 93.22 9.00 592.20 79.90 69.91 296.10 197.40 148.05 118.44 98.70 9.50 625.10 312.55 84.60 74.03 208.37 156.28 125.02 104.18 89.30 10.00 658.00 329.00 219.33 78.14 164.50 131.60 109.67 94.00 82.25 10.50 690.90 345.45 230.30 172.73 138.18 115.15 98.70 86.36 11.00 723.80 361.90 241.27 180.95 11.50 144.76 120.63 103.40 90.48 756.70 378.35 252.23 189.18 151.34 12.00 789.60 126.12 108.10 94.59 394.80 263.20 197.40 157.92 131.60 12-50 822.50 112.80 98.70 411.25 274.17 205.63 164.50 137.08 13.00 855.40 427.70 117.50 102.81 285.13 213.85 171.08 142.57 122.20 13.50 888.30 444.15 106.93 296.10 222.08 177.66 148.05 126.90 14.00 921.20 460.60 307.07 111.04 230.30 184.24 153.53 131.60 115.15 14.50 954.10 477.05 318.03 238.53 190.82 159.02 136.30 119.26 15.00 987.00 493.50 329.00 246.75 15.50 197.40 164.50 141.00 123.38 1019.90 509.95 339.97 254.98 203.98 16.00 169.98 145.70 127.49 1052.80 526.40 350.93 263.20 210.56 16.50 1085.70 175.47 150.40 131.60 542.85 361.90 271.43 217.14 180.95 17.00 1118.60 155.10 135.71 559.30 372.87 279.65 223.72 186.43 17.50 1151.50 159.80 139.83 575.75 383.83 287.88 230.30 191.92 18.00 1184.40 164.50 143.94 592.20 394.80 296.10 236.88 197.40 18.50 1217.30 608.65 169.20 148.05 405.77 304.33 243.46 202.88 173.90 19.00 1250.20 625.10 152.16 416.73 312.55 250.04 208.37 178.60 19.50 1283.10 641.55 427.70 156.28 320.78 256.62 213.85 183.30 160.39 20.00 1316.00 658.00 438.67 329.00 20.50 263.20 219.33 188.00 164.50 1348.90 674.45 449.63 337.23 269.78 21.00 224.82 192.70 168.61 1381.80 690.90 460.60 345.45 276.36 21.50 230.30 197.40 172.73 1414.70 707.35 471.57 353.68 282.94 22.00 235.78 202.10 176.84 1447.60 723.80 482.53 361.90 289.52 22.50 241.27 206.80 180.95 1480.50 740.25 493.50 370.13 296.10 23.00 246.75 211.50 185.06 1513.40 756.70 504.47 378.35 302.68 24.00 1579.20 252.23 216.20 189.18 789.60 526.40 394.80 315.84 263.20 24.50 1612.10 225.60 197.40 806.05 537.37 403.03 322.42 268.68 25.00 1645.00 230.30 201.51 822.50 1 54833 41125 329.00 274.17 235.00 205.63 Enter % Enter Change Time Flow Rate 42
BwOP WX-501T1 Revision 19 Continuous Use NOTE Closing the OAOV-WX889 will isolate sample flow to the ORE-PR001, thus causing it to interlock, and subsequently close the applicable flow path's Release Tank Discharge Isolation Valve (0A9V-WX353 or OAOV-WX896).
G. 17. IF the r9lease MUST be Interrupted to ptovide the opeotor'a break when a relief
" unaeaila1e, is THEN perform the following:
- a. Receive permission from the Shift Manager to secure the release for no more than 30 minutes.
- b. Make a log entry and an entry on the table in step G.16. denoting the time the release was stopped.
- c. OPEN OAOV-WXOI5, Release Tank Pump 0WX01P Recirc Valve.
NOTE Notify Main Control Room prior to closing OAOV-WX889 as this action will generate an RM-1 1 alarm.
- d. CLOSE 0AOV-WX889, Release Tank Pump 0WX01P Discharge Isol Valve.
- e. VERIFY that the release has been stopped.
- f. MINIMIZE the pause in the release.
- g. NOTIFY Shift Manager that release will be started again.
- h. Make a log entry and an entry on the table in Step G.16. denoting the time which the release was restarted.
- i. OPEN OAOV-WX889, Release Tank Pump 0WX01T Discharge Isol Valve.
- j. VERIFY Release Tank Discharge Header Radiation High alarm at OPLO1J CLEARS.
43
BwOP WX-501T1 Revision 19 Continuous Use NOTE Upon receipt of a high radiation signal at OPRO1J, the Release Tank Discharge Valves, 0WX353 and 0WX896 will remain closed until the high radiation signal seal-in is reset at OPLOIJ.
- :. ,__17,... 4!,-YE
- .F-IFY,/OPEN 0A0V-.WX.353/9, -R61ea"e akD c ag ,Ioato ;.**...
Valve, for the flow path being used.
I. CLOSE 0AOV-WX015, Release Tank0WX01T P.umpRecirc Valve.
NOTE Tripping the release tank pump will stop sample flow to the ORE PR001 ,thus causing it to interlock. The main control room should be notified prior as this will generate an RM-1 1 alarm.
- 18. WHEN the desired volume of water has been released from Release Tank OWX01T, TRIP Release Tank Pump OWX01P.
NOTE Verification is required for step G.19. if ORE-PRO01 is inoperable and AAR OBwOS RETS 2.1-la has been initiated.
- 19. CLOSE OAOV-WX3021897, Release Tank Discharge Flow Control Valve.
SUPERVISOR VERIFICATION
- 20. RECORD the following:
- a. Release Stop Time: Date:
- b. Tank Level Final %
- c. Batch Totalizer Reading xl0 = gals (if operable)
- d. Cumulative Totalizer Reading Final xlO = gals (if operable) 44
BwOP WX-501T1 Revision 19 Continuous Use 4 .
NOTE At low release rates or if Batch and Cumulative Totalizers are inoperable, the gallons released may be calculated by multiplying the percent decrease in tank level by 329 gallons.
"( _2. e .,RECORQGa.llprrsReleased.byane ofhe w : -* .. . ..,.
o TOTALIZER READING gallons Date:
o (-. J)X329.= gals (Step G.3.a. - Step G.20.b)
Calculation Date:
- f. NOTIFY the Shift Manager that the release is complete.
- g. NOTIFY the Control Room that the release is complete.
NOTE Verification is required for steps G.21. and G.23. if ORE-PR001 is inoperable and AAR 0BwOS RETS 2.1-1 a has been initiated.
- 21. VERIFY 0AOV-WX353, Release Tank Discharge Valve to Circ. Water Blowdown, LOCKED CLOSED.
SUPERVISOR VERIFICATION
- 22. RECORD time when key was removed from key lock switch for OAOV-WX353, Release Tank Discharge Valve to Circ. Water Blowdown.
(N/A if this flowpath was not used)
- 23. VERIFY 0AOV-WX896, Release Tank Discharge Valve to Circ. Water Blowdown, LOCKED CLOSED.
SUPERVISOR VERIFICATION
- 24. RECORD time when key was removed from key lock switch for OAOV-WX896, Release Tank Discharge Valve to Circ. Water Blowdown.
(N/A if this flowpath was not used)
- 25. CLOSE OAOV-WX889 Release Tank OWX01 P Discharge Isolation Valve.
45
BwOP WX-501T1 Revision 19 Continuous Use G. 26. If Relay Block K1 at ORE-PRO01 was removed in step G.2., then
- a. NOTIFY Shift Manager that the temporary Electrical Alterations being restored.
- b. REPLACE Relay Block Ki at ORE-PROO1, AND
- , SUPERVISOR VERIFICATION
- c. REMOVE the two placards stating "KI RELAY REMOVED FOR LIQUID RELEASE", that were placed in Step G.2.c .
- d. If the Electrical Alteration cannot be restored, process a temporary alteration.
- 27. Backflush the OPRO1J radiation monitor as follows:
- a. VERIFY release tank OWX01T is less than 2§%.
CAUTION Do not back flush the Radiation Monitor f~r a period of time such that the release tank level exceeds 91%.
NOTE Steps G.27.b. through G.27.n. may be omitted at OPS Supervisor discretion if ORE-PR001 is INOPERABLE and AAR-BwOS RETS 2.1-1a has been initiated.
NOTE NOTIFY the Control Room that you will be flushing 0PR01J and that they will be receiving an alarm on RM1 1.
- b. VERIFY/OPEN 0WM897, WM Header Isolation Valve
- c. CLOSE 0WX354, Release Tank Discharge to Process Rad Monitor System.
- d. OPEN 0PR052, WX discharge to ORE-PRO01 Sample Connection.
- e. OPEN OPRO50, OPR01J Backflush Isolation Valve 46
BwOP WX-501 T1 Revision 19 Continuous Use G 27. f. OPEN 0WM898, OPR01J WM Supply Header Valve
- g. WAIT 1 minute
- h. CLOSE 0PR5004, Skid OPROIJ Flow Isolation Valve
- i. FLUSH OPROIJ, Radiation Monitor for 15 minutes
- j. CLOSE OPRO50, OPRO1J Backflush IsolationValve
- k. CLOSE 0WM898, OPR01J WM Supply Header Valve
_I. OPEN 0PR5004, Skid OPRO1J Flow Isolation Valve
- m. CLOSE 0PR052, WX discharge to ORE-PR001 Sample Connection.
- n. OPEN 0WX354, Release Tank Discharge to Process Rad Monitor System
- o. Perform the following:
- 1) OPEN "NO EPN", OPROIJ Return to OWX26T.
- 2) CLOSE "NO EPN", OPR01J Return to 0WX01T.
- 3) Update Placard on Radwaste Control Panel to indicate that OPROIJ is lined up to OWX26T.
- 28. OPS Supervisor: I have reviewed Part G and have verified it is accurate and complete.
OPS Supervisor teI Ti Date Time 47
BwOP WX-501T1 Revision 19 Continuous Use H. CONTROL ROOM SUPERVISOR RESPONSIBILITY NOTE If the current activity level recorded in step H. 1. is greater than 1.31 E-4 ipCi/ml, INITIATE a work request to decontaminate the ORE-PR001 sample chamber.
I. RECORD the current reading for ORE-PR001 (OPSI01).
miCi/ml Date:
NOTE Step H.2.a. is not required if ORE-PRO01 is inoperable and AAR 0BwOS RETS 2.1-1a has been initiated. Step H.2.b. is not tequired if ORE-PR010 is inoperable and AAR 0BwOS RETS 2.1-1a has been initiated.
- 2. SET the Rad Monitor ORE-PR001 (OPS101) and ORE-PR010 (0PS1 10) to their original setpoints as follows:
- a. RESET the ALERT Alarm and HIGH Alarm setpoints for ORE-PRO01 (OPS101) to their original values by performing the following:
VERIFICATION
- 1) PLACE the RM-1l Console in SUPERVISOR MODE.
- 2) SELECT the ALERT alarm setpoint (channel item 10) to be changed on the ORE-PR001 (OPS101) CHAN ITEMS display by KEYING in 10 and DEPRESSING the SEL key. (Following this CHAN ITEM 10 should be displayed in reverse characters.)
- 3) ENTER the original ALERT alarm setpoint USING the format XYZ +/- AB. The CHAN ITEM 10 ALERT Alarm setpoint is 6.56E-5 pCi/ml, enter this as 6.56-5 and DEPRESS the ENTER key. The new value will be displayed after a short delay.
- 4) SELECT the HIGH alarm setpoint (channel item 9) to be changed on the ORE-PR001 (OPS101) CHAN ITEMS display by KEYING in 9 and DEPRESSING the SEL key. (Following this CHAN ITEM 9 should be displayed in reverse characters.)
48
BwOP WX-501 T1 Revision 19 Continuous Use H. 2. a. 5) ENTER the original HIGH alarm setpoint USING the format XYZ +/- AB. The CHAN ITEM 9 HIGH Alarm setpoint is 1.31 E-4 i.Ci/ml, enter this as 1.31-4 and DEPRESS the ENTER key. The new value will be displayed after a short delay.
- b. RESET the ALERT and HIGH setpoints for ORE-PR010 to their original values by performing the following:
VERIFICATION
- 1) SELECT the ALERT alarm setpoint (channel item 10) to be changed on the ORE-PRO10 (OPS1 10) CHAN ITEMS display by KEYING in 10 and DEPRESSING the SEL key. (Following this CHAN ITEM 10 should be displayed in reverse characters.)
- 2) ENTER the original ALERT alarm setpoint USING the format XYZ +/- AB. The CHAN ITEM 10 ALERT Alarm setpoint is 5.73E-6 XCi/ml, enter this as 5.73-6 and DEPRESS the ENTER key. The new value will be displayed after a short delay.
- 3) SELECT the HIGH alarm setpoint (channel item 9) to be changed on the ORE-PR010 (OPS1 10) CHAN ITEMS display by KEYING in 9 and DEPRESSING the SEL key. (Following this CHAN ITEM 9 should be displayed in reverse characters.)
- 4) ENTER the original HIGH alarm setpoint USING the format XYZ +/- AB. The CHAN ITEM 9 HIGH Alarm setpoint is 8.19E-6 pCi/ml, enter this as 8.19-6 and DEPRESS the ENTER key. The new value will be displayed after a short delay.
- 5) PLACE the RM-1 1 Console in the NORMAL MODE.
49
BwOP WX-501T1 Revision 19 Continuous Use NOTE DO NOT isolate Circulating Water Blowdown until at least three and one-half Q. hours after the release stop time recorded in step G.20.a. to ensure the entire release tank effluent]has passed through the Circulating Water Blowdown pipe to the Kankakee River.
Control of Circulating Water Blowdown Flow Limitations may be transferred to an Equipment Status Tag for the purpose of ,
completing this package. The Equipment Status Tag must specify the time and date for completion of the 3.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> flush requirement.
This method is most applicable when performing multiple releases in one day. If control is transferred to an Equipment Status Tag, Step H.3. may be marked as "Condition Met".
H 3. 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> or more after the time recorded in step G.20.a., REMOVE the placard stating "Liquid Release in Progress" at OPMO1J.
- 4. RECORD the Time and Date "Liquid Release'in Progress" placard is removed at OPMOIJ:
Time: Date:
- 5. FORWARD this form to Health Physics to complete Section I.
50
BwOP WX-501T1 Revision 19 Continuous Use
- 1. HEALTH PHYSICS SUPERVISION NOTE If a computerized release program is available, you may attach the printout to this form and indicate "see attached" in the calculation spaces in step 1.1. below.
1: COMPLETEthe table below for each isotope d&eIttli68 in step D.6.a.:
Total Activity Isotope RTotal Actvity Isotope. Released (ICi) IsotopeReleased (urih 4
4.
I. I i
4.
Sum of activities above =
OBTAIN by multiplying each number in column #2 of table in step D.6.a. by total volume released from step G.20.e. (in ml)(ml=gal x 3785)
Total ml released = rml
- 2. Health Physics Supervision SHALL VERIFY compliance with 10CFR50 dose limits, as specified in ODCM Radioactive Effluent Technical Standard 12.3.2.A, by ENTERING release data into the 10CFR50 ODCM Liquid Release Program per BwRP 6110-8.
(Final) 51
JOB PERFORMANCE MEASURE TASK TITLE: Classify and Screen an Zvont for Reportability JPM No.: 8-05 REV: 12 TPO No.: IV.F.ZP-17 K&A No.: (2.4.30)
TASK No.: S-AM-102 K&A IMP: 2.2/3.6 TRAINEE:
EVALUATOR:____________
DATE:
The Trainee: PASSED this JPM. TIME STARTED:
FAILED TIME FINISHED:
CRITICAL ELEMENTS: (*) 2, 3 JPM TIME: MINUTES CRITICAL TIME: 15 min for #2 APPROX COMPLETION TIME: 6 MINUTES EVALUATION METHOD:
LOCATION:
x PERFORM IN PLANT SIMULATE SIMULATOR GENERAL
REFERENCES:
- 1. Exelon Reportability Manual, Operations Decision Tree,
- 2. Braidwood EALs.
LS-AA-1020 MATERIALS:
Copies of the references listed above.
TASK STANDARDS:
- 1. Classify the event per the Braidwood EALs.
- 2. Determine all reporting requirements per the Exelon Reportability Manual.
- 3. Demonstrates the use of good Core Work Practices.
TASK CONDITIONS:
- 1. You are the Unit 1 Unit Supervisor.
- 2. Unit 1 is in Mode 6 with refueling in progress.
- 3. All systems required to be operable in Mode 6 are functioning normally.
INITIATING CUES:
- 1. While supervising core alterations, the FH Supervisor was hit on the head by a piece of wood dropped from the top of the S/G shield wall.
He was knocked unconscious and fell into the contaminated refueling cavity.
- 2. The injury requires medical attention and he is now enroute to St. Joseph Medical Center with a Rad Tech and an engineering assistant via Braidwood ambulance.
- 3. The SM directs you to evaluate for the Emergency Plan and determine all reporting requirements per the Bwd EALs, and the Exelon Reportability Manual.
s-o5 (7/5/01) 1
PERFORMANCE CHECKLIST STANDARDS SAT UNSAT N/A RECORD START TIME
- 1. Refer to Exelon Locate and Open the 0]
Reportability Manual and 03 []
following:
Braidwood EALs.
"* Exelon Reportability Manual.
"* Braidwood EALs.
- 2. Evaluate for GSEP. Using Braidwood EALs, Cold Initiating [] 0 0 Conditions, determine the Emergency Plan (Not*: Record time to classification:
classify_ .
Must be < 15 minutes from start
- Unusual Event HU?
time.)
- 3. Screen the event for Using the Exelon [] 03 03 Reportability. Reportability Manual decision Trees to determine:
" Emergency Plan Activated - SAF 1.1.
" SAF 1.1 requires notification of State and Local within 15 minutes; and NRC within I hour.
"* Transport to Medical Facility - SAF 1.1 and RAD 1.6.
" RAD 1.6 requires notification of NRC within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
(However the 1 hr notification for SAF 1.1 takes precedence over the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> notification, and no duplicate call is necessary.)
o 30 day LER (CUE:) THIS COMPLETES THIS JPX.
RECORD STOP TIME COMMENTS:
2 S-05 (7/5/01)
TASK CONDITIONS:
- 1. You are the Unit 1 Unit Supervisor.
- 2. Unit 1 is in Mode 6 with refueling
- 3. All systems required to be operable inin progress.
Mode 6 are functioning normally.
INITIATING CUES:
- 1. While supervising core alterations, the FH Supervisor on the head by a piece of wood dropped from the was hit shield wall. top of the S/G He was knocked unconscious and fell into the contaminated refueling cavity.
- 2. The injury requires medical attention and St. Joseph Medical Center with a Rad Tech he is now enroute to and an engineering assistant via Braidwood ambulance.
- 3. The SM directs you to evaluate for Emergency Plan all reporting requirements per the Bwd EALs, and and determine the Exelon Reportability Manual.
3 S -0 5 (7 /5 /01)
SIMULATOR SETUP INSTRUCTIONS JPM NO: S-05 REQUIRED SIMULATOR MODE(S): ANY MALFUNCTION #'S: N/A COMMENTS:
- 1) This JPM may be performed IN PLANT or in Simulator.
4 S-05(7/5/01)
'0 a
.2
.3 U
II U
I iii C,,
I II I
Ii.
0 ji Iii I
I S
I S*1 0
I a
- 1 Pj .1 I
II *1 I I I
.3 I ii I .9a ill I.
I I I
'a E
I..
I-sI 0
I I I I
I I I II
'H ii' I I
I I
Ie N
0 I
I
)
91.ýAvu,mnAn A nno~v l*.Telnn Mnnel*mr RECOGNITION CATEGORY HAZARDS AND OTHER CONDITIONS
) MATRIX DESCRIPTION HU7" Transportation of Radioactively Contaminated Peson(s) to an Offsite Medical Facility.
INITIATING CONDITION Transportation of radioactively contaminated person(s) to an offsite medical facility.
,AI.,-TIMESHOLD VALUE A radioactively contaminated injured person(s) is transfeffed to an offsite medical facility for tmtment.
MODE APPLICABILITY ALL BASIS (Referescs.)
Tins EAL insues that prope" authorities aw notified when a row rnated or potentially contaminated individual is trensported to an offskte medical facility. If it is umcertain that the individual is contaminated an UNUSUAL EVENT should be conservatively declard mtil proven otherwinse.
T auN=~ / Ragoveff Conmdgrsbions A detmmination is made that the individual(s) is no looW coatoninsted HU7 January 2002 BW 3-73 Revision 9
LS-AA-I 110 Revision Date 01/23/01 Page 1 of 132 REPORTABLE E VENT SAF 1.1:
Declaration of Emergency Class Requirement: 10 CFR 50.72(aXlXi) 10 CFR 50 App. E,Section IV.D.3 10 CFR 72.75(a) 10 CFR 72.75(d)(2)
§ 50.72(aXIXi): Each ... licensee ... shall notify the NRC ... of... declaration of any of the Emergency Classes specified in the licensee's approved Emergency Plan.
§ 50 App. F,Section IV.D.3: ... notify responsible State and local government agencies within 15 minutes after declaring an emergency.
§ 72.75(a): Each licensee shall notify the NRC ... upon the declaration of an emergency as specified in the licensee's approved emergency plan.
172.75(d)(2): Each licensee ... shall submit a written follow-up report within 30 days of the initial notification.
Time Required Notification(s):
Limit 15 MIN Notify State and local government agencies, in accordance with the Emergency Plan, within 15 minutes of declaring an emergency class. [10 CFR 50, Appendix E,Section IV.D.3]
30 MIN Notify State and local government agencies, in accordance with the Defueled Emergency Plan, within 30 minutes of declaring an emergency class. [10 CFR 50.72(a)]
1 HOUR Notify the NRC Operations Center via the ENS of the declaration of any of the Emergency Classes specified in the Emergency Plan immediately after notification of the appropriate State or local agencies and not later than one hour after the time the Emergency Class is declared. [10 CFR 50.72(aX)(1Xi), (aX3)]
(1-011 1 HOUR Activate the Emergency Response Data System (ERDS) as soon as possible but not later than one hour after declaring an Emergency Class of Alert, Site Area Emergency/Site Emergency, or General Emergency. [10 CFR 50.72(a)(4)] [1-311 Reportability Reference Manual
LS-AA-I 110 Revision Date 01/23/01 Page 2 of 132 REPORTABLE EVENT MELL W" V 1 HOUR Notify the NRC Operations Center upon the declaration of an emergency as specified in the Emergency Plan immediately after notification of the appropriate State or local agencies, but not later than one hour after the time the emergency is declared. [10 CFR 72.75(a)J[I-01]
HOURLY Verify that the Emergency Response Orgm=aton (ERO) updates the state' agencies hourly or as requested. A state agency update should be issued at the top of the hour plus or minus ten minutes, starting the second hour after an alert or higher classification is made. [Emergency Plan) 2 HOURS Notify ANI and INPO of the declaration of an Emergency Class of Alert, Site Area Emergency/Site Emergency, or General Emergency not later than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after the time the Emergency Class is declared. [1-271 AS REQ'D Notify the NRC Operations Center immediately during the course of the event of (i) any further degradation in the level of safety of the plant or other worsening plant conditions, or (ii) any change from one Emergency Class to another, or (iii) a termination of the Emergency Class. [10 CFR 50.72(cXIl)J[-25]
AS REQ'D Notify the NRC Operations Center immediately during the course of the event of (i) the results of ensuing evaluations or assessments of plant conditions, (ii) the effectiveness of response or protective measures taken, and (iii) information related to plant behavior that is not understood. [10 CFR 50.72(c)(2)][I-29]
Time Required Wriuten Report(s):
Limit 30 DAYS Submit a written follow-up report within 30 days of the initial notification.
[10 CFR 72.75(dX2)] [T-29](ISFSI)
Discussion:
o NRC guidance on this Reportable Event is provided in NUREG 1022, Revision 2, Section 3.1.1.
o Refer to the Emergency Plan and implementing procedures for identification of the specific events which require Emergency Plan activation.
Reportablity Reference Manual
LS-AA-I 110 Revision Date 01/23/01 Page 3 of 132 REOR TABLE FEVENT SA F L I (Cont1d) o If any doubt exists as to whether to initiate notification to the NRC Operations Center, the notification shall be made.
o The ERDS may also be activated during emergency drills or exercises if the licensee's computer system has the capability to transmit the exercise data.
o Notification of State and local agencies should be the first priority, followed by notification of the NRC. NUREG 0654, Revision I suggests that a written follow-up report be submitted to the NRC within 8 or 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, depending on the Emergency class, following close-out of the emergency or Emergency Class reduction.
o Declaration of an Emergency Class means that plant shi"t management has determined that conditions at the plant site meet the criteria specified in the Emergency Plan that define an Emergency Class, and the procedures for coping with that Emergency Class have been activated.
o Notifications and reports required by 10 CFR 72 pertain to conditions associated with an independent spent fuel storage installation (ISFSI).
o ANI should be advised of all emergency situations potentially involving bodily injury, damage to offsite property, or evacuation of offsite personnel in order that financial assistance and response plans can be initiated in a timely manner.
RelatedReportable Events:
o SAF 1.8, Event or Condition that Could Have Prevented Fulfillment of a Safety Function o SAF Y. 11, Operation or Condition Prohibited by Technical Specifications o SAY 1.19, Adverse Condition 0 SAY 1.23, Occurrence of an Incident o SAY 1.44, Impairments to Fire Suppression Systems Re--r Reporvabi/ity Reeec r manua aul .. .......
" =a"
- LS-AA-I I10 Revision Date 01/23/01 Page 4 of 132 REPORABLI*:E NT SFI.Cont'd,
)
References:
o 10 CFR 50, Appendix E, Section IV.C o NUREG 0654, Revision I o NUREG 1022, Revision 2 o NRC Information Notice 80-06, "Notification of Significant Events at Operating Power Reactor Facilities," February 190o.
o NRC Information Notice 88-64, "Reporting Fires in Nuclear Process Systems at Nuclear Power Plants," August 1988.
o Plant specific Emergency Response Procedures o ANI Information Bulletin SA(8 1), "Accident Notification Procedures for Property and Liability Insureds" o INPO 86-032, Emergency Resources Manual U) o !0 CFR 50.72 o 10 CFR 50.73 Repornabfiuty Reference Manual
LS-AA-1 120 Revision Date 01/23/01 Page 21 of 98 REMORTABLE E [YmT RAd&1,$ (CoL'd o The dose from planned special exposures is not to be considered in controlling future occupational dose of the individual but is to be included in evaluations required for other planned special exposures.
Related ReportableEvents:
"o RAD 1.1 , Events Involving Byproduct,.Source or Special Nuclear Mat!i That Cause or Threaten to Cause Significant Exposure or Release "o RAD 1.2, Events Involving Loss of Control of Licensed Material That Cause or Threaten to Cause Exposure or Release "o RAD 3.1, Evenits Involving Byproduct, Source, or SNM Causing Significant Exposure or Release 0 RAD 3.2, Events Involving Licensed Material Causing Exposure or Release "o RAD 3.3, Individual Exposure w"- -.,aion Levels (Unplanned or Planned Special Exposures)
References:
o 10CFR 19.13 o 10 CFR 20 ReportabilityReference Manual
LS-AA-1 120 Revision Date 01/23/01 Page 22 of 98
)
THIS PAGE INTENTIONALLY LEFT BLANK 31 Reportability Reference Manual
LS-AA-I 120 Revision Date 01/23/01 Page 23 of 98 REPORTABLE E VENT RAD 1. 6:
Transport of Contaminated Person to Medical Facility Requirement: 10 CFR 50.72(bX3Xxii) 10 CFR 72.75(bX5) 10 CFR 72.75(dX2)
§ 50.72(bX3)(xii): The licensee shall notify the NRC as soon as practical and in all cases, within eight hours of occurrence of... any event requiring the transport of a radioactively contaminated person to an offsite medical facility for treatment.
§ 72.75(bX5): Each licensee shall notify the NRC as soon as possible but not later than four hours after the discovery of any ... events or conditions involving spent fuel or HLW
... that requires unplanned medical treatment at an offsite medical facility of an individual with radioactive contamination on the individual's clothing or body which could cause further radioactive contamination.
§72.75(d)(2): Each licensee ... shall submit a written follow-up report within 30 days of the initial notification.
Time RequiredNotfication(s):
Limit 4 HOURS Notify the NRC Operations Center as soon as possible but not later than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after discovery of an event or condition involving spent fuel or HLW that requires unplanned medical treatment at an offsite medical facility of an individual with radioactive contamination on the individual's clothing or body which could cause further radioactive contamination. [10 CFR 72.75(bX5)] [F-I 1]
8 HOURS Notify the NRC Operations Center via the ENS as soon as practical and in all cases within eight hours of the occurrence any event (that occurred within 3 years of the date of discovery) requiring the transport of a radioactively contaminated person to an offsite medical facility for treatment. [10 CFR 50.72(bX3Xxii)]
[E-05]
AS REQ'D Notify the NRC Operations Center immediately during the course of the event of (i) any further degradation in the level of safety of the plant or other worsening plant conditions, or (ii) any change from one Emergency Class to another, or (iii) a termination of the Emergency Class. [10 CFR 50.72(c)(1) [I-25]
ReportabiltyReference Manual
LS-AA-1 120 Revision Date 01/23/01 Page 24 of 98 REPOIRTALE EVENT RAD L6 Want'dW AS REQ'D Notify the NRC Operations Center immediately during the course of the event of (i) the results of ensuing evaluations or assessments of plant conditions, (ii) the effectiveness of response or protective measures taken, and (iii) information related to plant behavior that is not understood. [10 CFR 50.72(cX2)J[I-29J Time Required Written Report(s):
Limit 30 DAYS Submit a written follow-up report within 30 days of the initial notification made in accordance with § 72.75(bX5). [10 CFR 72.75(dX2)] [T-291 Discussion:
o NRC guidance on this Reportable Event is provided in NUREG 1022, Revision 2, Section 3.2.11. Reporting under § 50.72 is only required if this Reportable Event occurred within three years of the date of discovery.
o Treatment refers to any medical treatment whether or not such treatment is related to the contamination. If it has been determined prior to transport that the person and clothing is not contaminated, then no report is necessary.
o An offsite medical facility is a hospital or other facility that is capable of treating radioactively contaminated persons.
RelatedReportableEvents:
o SAF 1.1, Declaration of Emergency Class o SAF 1.27, Bodily Injury or Property Damage From Radioactive Material
References:
o 10 CFR 50.72 o i0 CFR 72.75 Reporfability Reference Manna/
PERFORMANCE CHECKLIST STANDARDS SAT UNSAT N/A JOB PERFORMANCE MEASURE TASK TITLE: Complete Unit Common Shiftly/Daily Surveillances JPM No.: N-02SHDLY REV: 0 TPO No. :
K&A No. 2.1.8 TASK No.:
K&A IMP: 2.9 TRAINEE:
EVALUATOR:
DATE:
The Trainee: PASSED this JPM.
TIME STARTED:
FAILED TIME FINISHED:
CRITICAL ELEMENTS: (*)5,9 JPM TIME:_ MINUTES CRITICAL TIME: N/A APPROX COMPLETION TIME 9 MINUTES EVALUATION METHOD:
X PERFORM LOCATION:
SIMULATE IN PLANT X SIMULATOR GENERAL
REFERENCES:
- 1. OBwOSR 0.1-0 Unit Common All Modes/At All Times Shiftly and Daily Operating Surveillance MATERIALS:
Copy of partially completed OBwOSR 0.1-0 TASK STANDARDS:
- 1. Perform actions necessary to complete
- 2. shiftly/daily surveillances Properly identify out of specification readings TASK CONDITIONS:
- 1. You are the Unit NSO.
- 2. Unit 1 is in Mode 1
- 3. Complete the Unit Common Shiftly/Daily Operating Surveillance for Shift 1
- 4. Current time is 0430 INITIATING CUES:
- 1. The Admin NSO on Unit 1 has been assigned an emergent did not complete the Unit Common task to perform and shift 1. You have been assigned Shiftly/Daily Operating Surveillances for by the US to complete the Unit Shiftly/Daily surveillance, OBwOSR Common 0.1-0.
1 N-
PERFORMANCE CHECKLIST STANDARDS SAT UNSAT N/A RECORD START TIME
- 1. Refer to OBwOSR 0.1-0 Locate and Open OBWOSR 13 3 03 0.1-0 (CUE: Provide examinee partially completed copy of OBwO8R 0.1-0)
- 2. Verify Ultimate Heat Sink Record Lake Water Level o 3 3 Operability from OLI-CW041 (as found)OLI-CW041
- 3. Check Meteorological Record Meteorological Monitoring Instrumentation Monitoring Data: 0 0 0]
(as found)OUR-EMool
- 34' Wind Speed (OUR EM001)
(as found)OUR-EM012
- 203' Wind Speed (OUR EM012)
(as found)OUR-EMool 0 34' Wind Direction (OUR-EM001) 0 203' Wind Direction (as found)OUR-EM012 (OUR-EM012
- Air Temp Delta T (OUR (as found) OUR-EM002 EM002)
- 4. Check Radiological Effluent Record Liquid Effluent Monitoring Instrument Monitoring Inst 0 0[ 0 (as found)OUR-CW032
- Station Blowdown (OUR CW032)
- 5. Verify Control Room Vent Record Control Room Operability Temperature 03 0 0 (917- 93°F) OTI-VC032 o CR Temp (OTI-VC032)
"* Identify temp reading above acceptance criteria
"* Red Circle log reading o Inform US of out of spec condition 2
N-
PERFORMANCE CHECKLIST STANDARDS SAT
- 6. Verify Aux Building UNSAT N/A Record Aux Bldg Exhaust Exhaust Operability Temperatures 0 0 0 (as found)OTI-VA033 (as found)OTI-VA034 "* Plenum OA (OTI-VA033)
"* Plenum OB (OTI-VA034)
- 7. Verify CST Level Record Condensate Storage Tank Level 0 03 0 (as found) lLI-CDO51A 0 1LI-CDO51A (as found)2LI-CD051A & 2LI-CDO51A
- 8. Verify surveillance Review remainder of completion surveillance for 0 0 0 completion.
"* Pages (D-2)-(D-10)
"* TRM 3.7.d.1 data attached
"* Unlocked fire door checks complete and attached
- 9. Complete Data Package Review and sign completed Cover Sheet (Page D-l) surveillance on NSO 0 0 0 signature block under (CUE: Current time is initial review 0435 if asked) (Page D-l)
Surveillance within acceptance criteria w/o reliance on a TS or TRM block - checks NO US is informed of out of spec reading on CR temp if not informed earlier (CUE:) THIS COMPLETES THIS JP1.
RECORD STOP TIME COMMENTS:
3
TASK CONDITIONS:
- 1. You are the Unit NSO.
- 2. Unit I is in Mode1
- 3. Complete the Unit Common Shiftly/Daily Operating Surveillance for
- 4. Current time is 0430 Shift 1 INITIATING CUES:
- 1. The Admin NSO on Unit 1 has been assigned an emergent did not complete the Unit task to perform and Common Shiftly/Daily Operating shift i. You have been assigned Surveillances for by the US to complete the Shiftly/Daily surveillance, Unit Common OBwOSR 0.1-0.
4
SIMULATOR SETUP INSTRUCTIONS JPM NO: N-02SHDLY REQUIRED SIMULATOR MODE(S)
- NA OVERRIDES #'S:
Override XCR air temp meter OTI-VC032 (ZAOOTIVC032) to 920F COMMENTS:
"* Place Release in Progress sign up
"* Need a supply of red pens out on back desk 5
N-
OBwOSR 0.1-0 Revision 3 Information Use ADMINISTRATIVE NSO UNIT COMMON ALL MODES / AT ALL TIMES SHIFTLY AND DAILY OPERATING SURVEILLANCE DATA PACKAGE COVER SHEET TODAYS DATE:
START TIME / COMPLETION TIME I I I Present UNIT I IUNIT 2 MODE j I Surveillance within ACCEPTANCE CRITERIA without YES No YES NO YES NO reliance on a Tech Spec / TRM / ODCM / AAR Action Y N Statement? 0 13 0 13 0 Surveillance completed on time? YES NO YES NO YES NO (0500 / 1400/2200 respectively) 0 0 0 0 0 0 Applicable Surveillance Data Sheets listed on D-10 YES NO YES NO YES NO attached? 0 0 0 0 3 0 Shift Manager or designee notified for any "NO" N/A YES N/A YES N/A YES response to the above? 0 0 3 0 0 NSO (S'gn:
Applicable LCOARs / AARs in effect for any failed YES NO N/A YES NO N/A YES NO N/A ACCEPTANCE CRITERIA? 0 0 03 0 03 0 0 0 0 Applicable BwAP 1110-1's in effect for any failed YES NO N/A YES NO N/A YES NO N/A ACCEPTANCE CRITERIA? 0 0 0 0 0 0 0 0 0 Any parameters or attachments not completed within YES NO N/A YES NO N/A YES NO N/A specified shift logged on Unit Supervisor Turnover Log? 0 0 03 0 0 0 0 0 0 Unit Supervisor (Sign):
TIME DATE TIME-dATE TIME DATE Shift Manager (Sign):
TIME DATE TIME DATE 'TIME DATE COMMENTS:
Title Signature Date Remarks D-1
(
OBwOSR 0.1-0 UNIT COMMON ALL MODES I AT ALL TIMES Revision 3 SHIFTLY AND DAILY OPERATING SURVEILLANCE DATA SHEET Information Use I RHIFT 1 I RHIk"r 9 I M cwiac-r -aE*
ULTIMATE HEAT SINK OPERABILITY VERIFICATION (For local check, ,MEASURE to.distnc between the water surface and steal grating at the south side of the LSH)
PARAMETER INSTRUMENT INSTRUMENT VALUE LINTS ACCEPTANCE CRITERIA LAKE WATER LEVEL 03 OLI-CW041 or Ft TECH SPEC:
(INTAKE BAY WTR LVL) 0 LOCAL >1 Ft on OU-CW041 or i5 12'10" locally.
ADMI N: 2!5. 5 Ft.
Tech Specs: SR 3.7.9.1 (MODE 1-4 requirement, always performed) 3.7.9 tA= annJirahkm*
3.7.9 [As anfi~cabIe k ATffltI tIflAI **k,.rar%... *..fl. .. .. .a.. a..... .. -.
VI1 i r'r.LUI..Pl L MUIPI I IMUM -MN IIjurULI MI 1I IUIN L.t NNIPI [ :HI,-(.K.
- - - . ----- I .--- - I -
I rMT"Jr'VMP I IC II4 I IMUMIPN I LMAF1N:L INSTR I CHANNEL I INSTR CHANNELI INSTR I UNTS ACCEPTANCE CRITERIA CHK OK? VALUE I CHK OK? I VALUE I CHK OK?I VALUE i ......... i I I NIND SPEED 34' 0 OUR-EM001 or 0Y 0 N .6 CHANNEL CHECK SAT O Y4011 (Indicating as expected 203' 0 OUR-EM012 or 0Y [3 N pertaining to existing plant
[] Y4013 - 'conditions) (Recorders NIND DIRECTION 34' 0 OUR-EM001 or 0Y 0-N operating with all pens inking
'Deduct 3600 from 0 Y4012 OR computer readouts readings _ 3600) indicating properly) 2030OUR-EM012 or Q]Y O]N
[] Y4014
,IR TEMP 199-9 O-UR-EM002 or OY ON (DELTA T) 30Ft 0Y4016 I
-RM: TSR 3.3.c.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION FLOW MEASREMENT DEVICES CHANNEL CHECKS (CHANNEL CHECK shall
- onsist of verifying flow indication during periods of release. CHANNEL CHECK shell b6ene at leas once per24 houiw.on4eya oawhich continuous, periodic or batch releases are made.) t .
I PARAMETER INSTRUMENT INSTRUMENT VALUE INSTRUMENT VALUE INSTRUMENT VALUE LUNTS. -,ACCEPTANCE CRITERIA STATION BLOWDOWN INSTRUMENT ]0OUR-CW032 or ] OUR-CW032 or OUR-CW032 or .GPM. Channel Check Sat LINE RECORDED 0 F2400 0 F2400 F2400 INSTRUMENT VALUE " "_ _-"""
ODCM: 122.13B (3.c) R.0&OS RETS 2.1-1a Comments:
D-2
(
OBwOSR 0.1-0 UNIT COMMON ALL MODES /AT ALL TIMES Revision 3 SHIFTLY AND DAILY OPERATING SURVEILLANCE DATA SHEET Information Use O HILI
-. 11 I .*llllt=l" 1 . ruF'g
- LnL*r ,*
I CONTROL ROOM VENTILATION OPERABILITY VERIFICATION PARAMETER INSTRUMENT INSTRUMENT VALUE INS RUMENT VALUE VALUE UNITS ACCEPTANCE CRITERIA CONTROL ROOM INSTRUMENT O OTI-VC031 or OTI-VC0or-. ' -C031 or OF < 90OF TEMPERATURE @ RECORDED 0 OTI-VC032 0TI-VC2 , l-VC032 OPM02J INSTRUMENT
[VALUE...
Tech Specs. SR 3.7.11.1 TRM: TSR 3.7.d. I (Table T3.7.d-1, Function 12) "LCOAR: *L 3.7.11 & 1/2BwO TRM 3.7.d AREA TEMPERATURE MONITORING - AUX BUILDING EXHAUST PARAMETER INSTRUMENT INSTRUMENT VALUE INSTRUMENT VALUE INSTRUMENT VALUE AUX BLDG VENTILATION OTI-VA033 at Exhaust Plenum OA OPM02J ...
I UNITS
'F ACCEPTANCE CRITERIA 0
1050 F (if > 105 F and < 1220F, AUX BLDG VENTILATION OTI-VA034 at I'generate a CR to address the Exhaust Plenum 0B 0PM02J EQ concerns of the high temp)
TRM: TSR 3.7.d.1 (Table T3.7.d.1, Function 7) (Refer'to CR#A2001-0193) LCOAR: 1/2B-wL TRM 3.7.d RADIATION MONITORING INSTRUMENTATION CHANNEL CHECKS (Usira
_-____.._i______
PARAMETER INSTRUMENT CHANNEL INSTR CHANNL' INSTR CHANNEL INSTR UNITS ACCEPTANCE CRITERIA CHK OK? VALUE CHK-OK?: -VAttJE CHK OKVALUE '
Y 0 N tY FUEL BLDG FH INCIDENT ORIU-AR055 034 CVV -N " ' MR/HR Green Channel "fVAIL" light is (With Fuel in Fuel Storage MR/HR Key)
ON areas or Fuel BIdg) ORIU-AR056 1MY ON 0 Y OyN DA, .
(MR/HR Key) :"
MCR OUTSIDE AIR ORIU-PR031 (GAS N Y ON ., 0 Y 0 N 07l' ON PC/mi INTAKES (TRAIN A) Key) . 1 ORIU-PR032 (GAS I$ Y O N yYO.ý..
Key) SS E4.... 0 Y O N N MCR OUTSIDE AIR ORIU-PR033 (GAS PY [0N OY 0N OY ON pCi/mtl INTAKES (TRAIN B) Key)
ORIU-PR034(GAS %Y ON .Y ON OY ON JKey)I Tech Specsý SR 3.3.7.1 (Table 3.3.7-1, Function 1) and COAR: 0BwOL 3.3.7, 0BwOL 3.3.8, & OBwOL TRM 3.3.o SR 3.3.8.1 (Table 3.3.8-1, Function 1)
TRM: TSR 3.3.o.1 (Table 3.3.o-1, Functional).
Comments:
(
O8wOSR 0. 1-0 UNIT COMMON ALL MODES / AT ALL TIMES Revision 3 SHIFTLY AND DAILY OPERATING SURVEILLANCE DATA SHEET Information Use Q HII- 1 I .M--Irior *llCIr" C qJ I RADIATION MONITORING I INSTRUMENTATION CHANNEL .. CHECKS
. (Using
!Hi~ RM-11. . IF.Inot surwillU - ia~
- ,using RM-23) the 2**
PARAMETER INSTRUMENT I CURSOR I INSTR I CURSOR INSTR I CURSOR I INSTR UNITS ACCEPTANCE CRITERIA I I COLORI VALUE I COLOR I VALUE COLOR I VALUE If RM-1 1 Printout is being used, Cursor colors are indicated as follows: G=Green, WzWhlte, Y=Yelow, M=-Magenta, B=Dark Blue, C=Light Blue, R=Red, c=Cyan.
Initial If Printout of RM-1 1 Group #25 Is Monitor Status is NOT Magenta (M),
Attached And Verified Acceptable /AWhite (f O Dark Blue(B).
(MWi (Dark Blue is acceptable if process flow NOT in use).
If writing data off RM-1 1 screen, Cursor color may be indicated as follows: G=Green, W=White, Y=Yellow, M=Magenta, DB=Dark Blue,is LB=Light Blue, R=Red, C=Cyan.
FUEL BLDG FH INCIDENT ORE-AR055 MR/HR ursor NOT Magenta, White, (With Fuel in Fuel Storage (G4 3AS155)
- _______ o_ Dak Blue.
areas or Fuel Bldg) ORE-AR056 Dark Blue is acceptable if (G4 3AS1 56) * . ," - rocess flow is NOT in use).
MCR OUTSIDE AIR ORE-PRO31 PCi/ml INTAKES (TRAIN A) (G2 OPB131) 6 _ "_ .... . __ ,
MCR OUTSIDE AIR ORE-PRO32 (G2 0PB1321 ORE-PR033 6 _ _-__-.__
INTAKES (TRAIN B) (G2 OPB133) 6 _. _ ___ .... - "
PC.VmI
________________ ORE-PR034 (G2 0PB1 34) __ __ g(- 6 _ __ __
Tech Specs: SR 3.3.7.1 (Table 3.3.7-1, Function 1) and LCOAR: BWL 3.3.7, OBwOL 3.3.8, & OBwOL TRM 3.3.0 SR 3.3.8.1 (Table 3.3.8-1, Function 1)
TRM: TSR 3.3.o.1 (Table T3.3.o-1, Function 1)
Comments:
(
(
OBwOSR 0. 1-0 UNIT COMMON ALL MODES I AT ALL TIMES Revision 3 SHIFTLY AND DAILY OPERATING SURVEILLANCE DATA SHEET Information Use IUC 4IIIl I ausev- I IItJI L"I" *l i I~~ iI 0NIIT I a -MET I A MONITOR LOSS OF FLOW (Dark Blue) cursor status Is acceptable If the NOTE monitored procee.sstrew Is NOT In use. SOURCE CHECKS consist of either verification that the IPM14JB-2 (2PMi4JB-2) printout Indicated SOURCE CHECK automatically conducted with the absence of "Channel Source Check Failed" status, or check Is satisfactorily conducted manually.
RADIOACTIVE LIQUID EFFLUENT RADIATION MONITORING INSTRUMENTATION CHANNEL CHECKS (Using RM-1 1) If writing data off RM-1 1 screen, Cursor color may be indicated as follows: G=Green, W=White, Y=Yellow, M=Magenta, DB*Dark Blue, LB=Light Blue, R=Red, C=Cvan.
1 ......-
I
.. 1 I r rV ll I I--'. I1I40 I MUMINI 1.#UKOUK M1Inp INSTR VAI "=I ACCEPTANCE CRITERIA CURSOR I1VALUE ICOLOR CURSOR IVALUEI INSR ICOLOR INSTR I UNITS LIQUID RADWASTE ORE-PRO01 pCi/ml EFFLUENT LINE _(G10OPSI01) 6 _
Cursor NOT Magenta, White.
RCFC 1A & 1C TRN A 1RE-PRO02 or Dark Blue.
OUTLET LINE SOURCE CHECK SAT and (G1 1PS102)
Cursor NOT Magenta, White, RCFC 1B & 1D TRN B 1RE-PRO03 or Dark Blue.
OUTLET LINE (G1 1PS103) 1 RCFC 2A & 2C TRN A 2RE-PRO02 OUTLET LINE (G1 2PS102) G C&"
RCFC 2B & 2D TRN B 2RE-PRO03 OUTLET LINE G1 2PS103_
FIRE AND OIL SUMP ORE-PRO05 SOURCE CHECK SAT and DISCHARGE (G1 OPS105) G ME-d Cursor NOT Magenta, White, CONDENSATE POLISHER ORE-PRO41 or Dark Blue.
SUMP DISCHARGE .(G1 OPS141) 6 STATION BLOWDOWN ORE-PR010 LINE (G1 OPSllO) G _,____
i I M 2 Rf
-0 I -- " 1°'-1. -- --!2 . ... I
OBwOSR 0. 1 -0 UNIT COMMON ALL MODES I AT ALL'TIMES Revision 3 SHIFTLY AND DAILY OPERATING 6URVEJLLANIe DATA SHEET Information Use I .HII,-r 1 I dD1 -J L, I
- . I"' ! I 'JI-ull I a
.1 I RADIOACTIVE LIQUID EFFLUENT RADIATION MONITORING INSTRUMENTATION CHANNEL CHECKS (Using RM-11) Ifwriting data off RM-11 screen, Cursor color may be indicated as follows: G=Green. W=White. Y=Yellow. Minjoamtw DI-nwwfk RIua LIRinht RPhi R=R,4 r=muftu,
- - - - - -------- Y Y -
PARAMETER INSTRUMENT CURSOR EPTANCE CRITERIA r*1 n"3 CC HX UNIT 0 ORE-PRO09 -*.I OUTLET (G1 OPS1O9) Cursor NoT Magenta, White, or Dark Blue and SOURCE UNIT 1 1RE-PRO09 CHECK SAT (consist of
______(G1 1PS109).y 0 either verification that the UNIT 2 2RE-PRO09 1PM14JB-2 (2PM14JB-2)
(G1 2PS109) G %,1E-01 printout indicated SOURCE UNIT ONE PART 1RE-PRO28A CHECK automatically AUX BLDG G2 1PA228) ( s conducted with the absence VENT STACK GAS 1RE-PR028B of "Channel Source Check EFFLUENT (Low) (G2 1PB128) _ ________ Failed" status, or check is IODINE IRE-PRO28C satisfactorily conducted (G2 1PC328) 6 l.Z "d manually.)
GAS (High) 1RE-PR028D (G2 1PD428)
UNIT TWO PART 2RE-PRO28A AUX BLDG (G2 2PA228( S E*4 VENT STACK GAS 2RE-PRO28B EFFLUENT (Low) (G2 2PB128) G _.__"O1 IODINE 2RE-PRO28C 2PC328)
(.-__(G2 " 3A -#4
___ _____ GAS
__ ___ G2 2PD428)
(High)_ 2RE-PRO28D __ _ _ _______*
U-1 CNMT NOBLE 1RE-PR001B PURGE EFFL GAS (G2 1PB101) & .q4E'4 Cursor NOT Magenta, White, or Dark Blue U-2 CNMT NOBLE 2RE-PR01B PURGE EFFL GAS (G2 2PB101) W44
- I ODCM 12.2.2.B (1.a, 1b, 1c, 2.a. 2.b, 2.c. 5.a. &6) a I - l l , , m CoI - - -
D4
(
UNIT COMMON ALL MODES SHIFTLY AND DAILY OPERATING I AT ALL TIMES OBWOSR 0. 1-0 SURVEILLANCE DATA $MHET Revision 3 Information Use 0-7
(
UNIT COMMON ALL MODE$ I AT ALL TIMES "BWOSR SHIFTLY SHI ".E:SURVEILLANCE DATA SHEE 0.1-0 AND DAILY OPERATING
. Revision 3 Information Use stable CHANNEL for OAIT-GWo04 CHECK consists readingsofto verifying be accurate.
proper op.ratioo. of all Analyzes fr W EXPLOSIVE GAS M N RING- I.INSTNTAT IN CH NNEL COB .. ..-.......
InTheMain 8odv) mutberunnin
,,a'ulf "LLdt:CK SAT and OXYGEN conc S 2%
by volume when HYDROGEN conc is > 4% by volume 4.
if-.
rxrr -
- 1'
- I.)
1 i
0-4
UNIT COMMON ALL. MOEg / AT ALL TIMES SHIFTLY AND DAILY OPEW. OBWOSR 0.1-0
.ACE DATA $f Revision 3 Information Use NMT c'I I1" , . ..
~-~=r4_ .
4 4, 4
c
(
UNIT COMMON ALL MOOES / AT ALL TIMES SHIFTLY AND DAILY OPERATING OBWOSR 0. 1-0 SURVEILLANCU 4 OJJA.SHEET Revision 3 Information Use TT A FWMfA r -A i. . . . .. .. "
I .
.1 XflSr N..--.
D-10:.-.
(
OBwOSR 0.1-0 UNIT COMMON ALL MODES I AT ALL TIMFS . Revision 3 SHIFTLY AND DAILY OPERATING SURVEILLANCE OATA SHEET Information Use RM-1 I GRO #25 PRINTOUT+
ATTACH THE MIPUTER PRINTOUT HERE ETRANSPARENT TAPE)
Comments:
D-11 .I
(
OBwOSR 0. 1-0 UNIT COMMON ALL MODES I AT ALL TIMES SHIFTLY AND DAILY OPERATING SURVEILLANCE DATA SHEET Revision 3 Use Information SHIFTr 2 RM-1 1 GROUP #25 PRINTOUT ATTACH THE COMPUTER PRINTOUT HIERE (USE TRANSPARENT TAPE)'
A-D-12
l, UNIT COMMON ALL MODES AT L TIMES SHIFTLY AND DAILY OPERATING SURVEILLANCE DATA SHEET OR 0.1-O nwOSR
,.I, .
"u,'marionUSe (Firna) 0-13.
OBwOS TRM 3.7.d.1 Revision 0 Reference Use UO, Ul AND U2 ALL MODES/AT ALL TIMES AREA TEMPERATURE MONITORING SHIFTLY SURVEILLANCE DATA SHEET DATE OF PERFORMANCE:
IT ONE TURB BLDG INSTRUMENT & SHIFT ACCEPTANCE TEMPERATURES LOCATION 1 2 3 CRITERIA STARTING TIME FOR THIS DATA IIIIIII 1/1111111I11 SHEET EACH SHIFT: I/I/IIIIIIII PORTABLE INSTRUMENT ID NUMBER ////////// / //
EACH SHIFT: IIII I/II -/IIIIIIII/II Div 12 Misc Ele Equip Room 1TI-VE003 on s 1VE01J Div 12 ESF Switchgear Room 1TI-VX002 on s0 1VX02J 108F Div 12 Cable Spreading Room 1TI-VX003 on 1VX02J 108 0 F Div 11 ESF Switchgear Room 1A Diesel Generator Oil 1TI-VX001 on 1VX01J 1TI-VD047 on q
q s
1 108°F Storage Room IVDO1JA qg
- 132 0 F 1A Diesel Generator Room 1TI-VD053 on 1VD01JA E3Z $$
lB Diesel Generator Oil 1TI-VD049 on Storage Room 1VD01JB . . " 132 0 F lB Diesel Generator Room 1TI-VD063 1VW01JB an q $$$
Div 11 Misc Ele Equip Room 1TI-VE502 S 108'F 451' L-9 Div 12 Battery Room Hand-Held s 108OF Pyrometer .
Div 11 Battery Room Hand-Held IPyrometer S 108 0 F ENDING TIME FOR THIS DATA SHEET EACH SHIFT: I//I/IIIIIII 0400IIIIIIIIIII CERTIFY (BY INITIALLING IN SPACE PROVIDED) ALL DATA THAT ALL DATA IS ACTUALLY TAKEN AND WITHIN ( TAKEN & IN SPECIFIED LIMITS: SPEC
- CERTIFY ( BY INITIALLING IN SPACE BOTH NSO AND PROVIDED) THE NSO AND UNIT SUPERVISOR UNIT NOTIFIED OF INCOMPLETE OR OUT OF SPEC WA SUPERVISOR DATA (RECORD "N/A" IF PREVIOUS STEP NOTIFIED IF OK) REQ' D
$$ The Tech Spec (TRM TSR) is satisfied IF either:
- a. Ambient room temperature is K 122 0 F, OR,
- b. Ambient room temperature AND the EDG Control Cabinet Exhaust temperature (BOTH sides of cabinet) are K 132 0 F.
Administratively limted to a 655F to ensure that battery electrolyte temperature does not fall below 60 0 F. Contact System Engineering Electrical group to determine appropriate actions for room temperature below 65 0 F.
COMMENTS:
C-2
OBwOS TRM 3.7.d.1 Revision 0 Reference Use UO, Ul AND U2 ALL MODES/AT ALL *IMN*
AREA TEMPERATURE MONITORING SHIFTLY SURVEILLANCE DATA SHEET DATE OF PERFORMANCE:
IT ONE AUX BLDG INSTRUMENT & SHIFT ACCEPTANCE E-PERATURES LOCATION 1 2 3 CRITERIA TARTING TIME FOR THIS DATA //////l//I - ////////////i SHEET EACH SHIFT: ! I ///// !_I/1111111_,
RTABLE INSTRUMENT ID NUMBER ///////.//// .//////////
EACH SHIFT: IHI/I/I/IIII IAIIIIIIIIIII 1B Safety Injection- Pump 1TI-VAO78 -s -30O Cubicle _ 1 130OF lB Cent Charging Pump Cubicle 1TI-VA076 ý 122°F 1A Cent Charging Pump Cubicle 1TI-VA075 122 0 F 1A Safety Injection Pump Cubicl1e 1TI-VA077
- s 130 0 F 30 1A Residual Heat Removal Pump 1TI-VA079 Cubicle !c130OF 1A Containment Spray-Pump 1TI-VA081 Cubicle 1 1B C u b Residual i cl e Heat Removal Pump 1TI-VA080
" ! 130 0 F 3 O 1B Containment Spray Pump 1TI-VA082 ! 130OF 1Cub icle*
1F - -
wer Cable Spreading Room OTI-VC618 ! 108lF Train OA (IZ2)
ENDING TIME FOR THIS DATA 439' L-13
/IIIIIIIIIIII 81 F IIIIIIII SHEET EACH SHIFT: IaItoIIIII I II O CERTIFY (BY INITIALLING IN SPACE PROVIDED)
THAT ALL DATA IS ACTUALLY TAKEN AND WITHIN ALL DATA SPECIFIED LIMITS: TAKEN & IN SPEC
- CERTIFY (BY INITIALLING IN SPACE BOTH NSO AND PROVIDED) THE NSO AND UNIT SUPERVISOR NOTIFIED OF INCOMPLETE OR OUT OF SPEC UNIT
, SUPERVISOR DATA (RECORD "N/A" IF PREVIOUS STEP NOTIFIED IF OK)
REQ'D a If temperature in room 1Z2 is > 105 0 F, MONITOR temperature in rooms IZ3 and 1Z4 with a Hand-Held Pyrometer. RECORD results in the comments section.
COMMENTS:
D-3
OBwOS TRM 3.7.d.1 Revision 0 Reference Use UO, Ul AND U2 ALL MODES/AT ALL TIMES AREA TEMPERATURE MONITORING SHIFTLY SURVEILLANCE DATA SHEET DATE OF PERFORMANCE:
IT TWO TURB BLDG INSTRUMENT &
TEMPERATURES SHIFT ACCEPTANCE LOCATION CRITERIA STARTING TIME FOR THIS DATA ///////////// ////////////i HERT FAcH. SHIFT.:
PORTABLE EAC SHIFT: INSTRUMENT ID NUMBER IIIIIIII
, IIII7111111111, S !lllllllll,,,
Div 22 Misc Ele Equip 2VE01Ji*on 2TI-VE003 108°F iv 22 ESF Switchgear 2VX02J Room 2TI-VX002 on S 108OF Div 22 Cable Spreading Room 2TI-VX003 2VX02J on 19 S 108OF Div 21 ESF Switchgear Room 2TI-VX001 on 2A Diesel Generator Oil 2VXreJ 2TI-VD047 11 on 108 0F Storage 2A DieselRoom DAT 2VD01JA Generator Room 2TI-VD053 on 132OF 2VD01JA *7$$
2B Diesel Generator Oil 2TI-VD049 on Storage Room -2VD01JB 11*1320F 2B Diesel Generator Room. 2TI-VD063 on Div 21 Misc Ele Equip 2TI-VES02 Div 21 Battery Room 4 51 L - 2 7 P C F D L I S1 08F Hand-Held Pyrometer T
- i 108OF Div 22 Battery Room Hand-Held yrometer
- 108OF ENDING TIME FOR THIS DATA Iiiiiii SHEET EACH SHIFT: Iii111/*1 CERTIFY (BY INITIALLING ISPACE PROVIDED) IIIIII THAT ALL DATA IS ACTUALLY TAKEN AND WITHIN AIIIIIIIIII SPECIFIED LIMITS: TAKLL DATA TAES&I CERTIFY (BY INITIALLING IN SPACE BOTH NSO AND PROVIDED) THE NSO AND UNIT SUPERVISOR UNIT NOTIFIED OF INCOMPLETE OR OUT OF SPEC SUPERVISOR DATA (RECORD "N/A" IF PREVIOUS STEP OK) NOTIFIED IF
$$ The Tech Spec (TRM TSR) is satisfied IF either: REO'D
- a. Ambient room temperature is s
- b. Ambient room temperature AND th-e-EDG 122 0 F, OR, Control Cabinet Exhaust temperature (BOTH sides or-cabinet)
- Administratively-l--mited 0 are ! 132 0 F.
to k 65 F to ensure t-at battery electrolyte temperature does not fall beloW-60 0 F. Contact System Engineering Electrical group to determine appropriate actions for room temperature COMMENTS:
OBwOS TRM 3.7.d.1 Revision 0 Reference Use U0, Ul AND U2 ALL MODES/AT ALL TIMES AREA TEMPERATURE MONITORING SHIFTLY SURVEILLANCE DATA SHEET DATE OF PERFORMANCE:
UNIT TWO AUX BLDG INSTRUMENT & SHIFT ACCEPTANCE TEMPERATURES LOCATION 1 2 3 CRITERIA STARTING TIME FOR THIS DATA I/'I / "//////////
SHERT EACH'SHI'Ft: "/I//I/Il// ,_._,I!!II _I_
PORTABLE INSTRUMENT ID NUMBER ///////f /////I///
! 1 / 11111 1 EA CH S HI F : .. .. . , III/ff / / _
2B Safety_Injection Pmp Cubicle __ 2TI-VA078,
_ __ _ .. . *_... . ... ___0_F"_
2B Cent Charging Pump Cubicle 2TI-VA076 ... 122 0 F 2A Cent Charging Pump Cubicle 2TI-VA075 s 1220F 2A Safety Injection Pump 2TI-VA077 Cubicle _ s_130_F 2A Residual Heat Removal Pump 2TI-VA079 s Cubicle _______0_F 2A Containment Spray Pump 2TI-VA081 ,
Cubicle s___130_F 2B Residual Heat Removal Pump 2TI-VA080 s 130OF Cubicle 1____730_F 2B Containment Spray Pump 2TI-VA082 s 130OF Cubicle . .[ ____"___30° Lower Cable Spreading Room 0TI-VC619 s 108°F Train 0B (QZ2) 439' L-23.5 21 _ _0_
Upper Cable Spreading Room OTI-VC620 V' 90°F Train OA (lEEI) 463' Q-16 #.
Upper Cable Spreading Room OTI-VC621 f 90°F Train 0B (2EEl) 463' Q-20 14# #
ENDING TIME FOR THIS DATA 7///7/////777 I/Il/l/l/7///
SHEET EACH SHIFT: 0 8_
oiiii/1/1 ___
CERTIFY (BY INITIALLING IN SPACE PROVIDED) ALL DATA THAT ALL DATA IS ACTUALLY TAKEN AND WITHIN P4: TAKEN & IN SPECIFIED LIMITS: SPEC
- CERTIFY (BY INITIALLING IN SPACE BOTH NSO AND PROVIDED) THE NSO AND UNIT SUPERVISOR UNIT NOTIFIED OF INCOMPLETE OR OUT OF SPEC 4A SUPERVISOR DATA (RECORD "N/A" IF PREVIOUS STEP NOTIFIED IF OK) REQ'D
- If temperature in room lEEl or 2EEl is > 870F, MONITOR temperature in rooms lEE2, lEE3, and lEE4 OR 2EE2, 2EE3 and 2EE4 with a Hand-Held Pyrometer for the associateT-Upper Cable Spreading Room train.
RECORD results in the comments section.
@ If temperature in room or 2Z2 is > 105 0 F, MONITOR temperature in rooms 2Z3 and 2Z4 with a Hand-Held Pyrometer. RECORD results in the comments section.
COMMENTS:
(Final) 11-r5
(
OBwOS FP.7.2.D-1 Revision 8 UNLOCKED FIRE DOOR DAILY Reference Use SURVEILLANCE Date: " 0%-- DATA SHEET (If additional
- DOORS MAYComment space CLOSED BE VERIFIED is needed, attach additional data sheet).
AND LATCHED BY ENSURING THAT THE SEAL, FROM THE DOOR TO FRAME, IS UNBROKEN. THE DOOR (Final)
D-2
TASK CONDITIONS:
- 1. You are an extra NSO.
- 2. The Unit 1 is at 100% power.
INITIATING CUES:
- 1. The US has provided you a copy of, the weekly QPTR calculation using and directed you to perform, process computer is inoperable lBwOSR 3.2.4.1. However only for the purpose of thisthe surveillance.
5 N-18 6/26/01
SIMULATOR SETUP INSTRUCTIONS
'-JPM NO: N-18 REQUIRED SIMULATOR MODE(S): 100% Steady State MALFUNCTION #'S: N/A COMMENTS: Use the following as a 'KEY' to check.calculations:
Date: TODAY Time: NOW Channel N41 N42 N43 N44 Is the channel operable? O Y ON OY ON QY ON [Y ON Instrument reading 100% 100% 100% 100%
UPPER DETECTORS (A)
Present upper detector current 190 185 190 185 100% upper detector current 194 179 192 186 Normalized detector current .979 1.03 .990 .994 Average normalized current .9m Upper power tilt ratio (0--1.02) 0.900 l 1.03 l .990 $.996 LOWER DETECTORS (B)
Present lower detector current 170 1150 165 165 100% lower detector current 170153 165 168
"-I Normalized detector current 1.00 1.960 11.0 1.962 Average normalized current .990" Lower power tilt ratio (0:51.02) 101.01 1 .969 #01.01 F0.991 6
N-18 6/26/01
UNIT ONE QUADRANT POWER TILT RATIO CALCULATION NIS METERS
- . 3eing performed once per:
O 7 Days (normal interval) "OShifily O 12 Hours (with BwVSR 3.2.4.2.) "oOther:
Date: TODAY Time: NOW Channel N41 N42 N43 N44 Is the channel operable? OY ON - OY ON OY ON OY ON Instrument reading 0%00% 100% 109%
________________ _ UPPERODETECTORS (A) '
Present upper detector current .- 190 .. 185. 190 186 100% upper detector current 194 179 192 186 Normalized detector current Average normalized current Uppe r p ower tilt ratio ( 0 51
.02 ) L D ( 8)
LOWER DETECTORS (B) '
Present lower detector current 170 150.1 165 165 100% lower detector current 170 153 165 168 Normalized detector current .
Average normalized current Lower power tilt ratio (0:51.02) '
Date: Time:
Channel N41 N42 N43 N44 Is the channel operable? QY ON [Y ON QY ON QY ON Instrument reading % % % %
UPPER DETECTORS (A)
Present upper detector current 100% upper detector current Normalized detector current Average normalized current Upper power tilt ratio (0:91.02) 1 LOWER DETECTORS (B)
Present lower detector current 100% lower detector current Normalized detector current Average normalized current Lower power tilt ratio (010.02)
Attach additional copies of this page as necessary.
"7 1 18 61/26,01
UNIT ONE QUADRANT POWER TILT RATIO CALCULATION NIS METERS
.3eing performed once per:
0 7 Days (normal interval) 0 Shiftiy 0 12 Hours (with BwVSR 3.2.4.2.)
0 Other:
Date: TODAY Time: NOW Channel N41 N42 Is the channel operable? QY n 3N Oy ON Instrument reading
. 100% 100%
UPPER OETECTORS (A)
Present upper detector current -190. .185 100% upper detector current 194 179 Normalized detector current Average normalized current Upper power tilt ratio ( $<1.02) L D i LOWER DETEi*CTORS (B)
Present lower detector current 170 150 100% lower detector current 170 153 Normalized detector current Average normalized current Lower power tl ratio (0<1.02)
Date: Time:
Is the channel operable? OY ON QY ON [
Instrument reading % %
UPPER D,-ETECTORS (A)
Present upper detector current 100% upper detector current Normalized detector current Average normalized current Upper power tilt ratio (0<1.02)
LOWER DE-TECTORS (B)
Present lower detector current 100% lower detector current Normalized detector current Average normalized current Lower power tilt ratio (<1.02) TO Attach additional copies of this page as necessary.
N-18 6/26/01 7
1BwOSR 3.2.4.1 Revision 2 Reference Use UNIT ONE QUADRANT POWER TILT RATIO (QPTR) CALCULATION A. STATEMENT OF APPLICABILITY This procedure outlines the steps necessary to verify the QUADRANT POWER TILT RATIO is ! 1.02. It is applicable in MODE 1 above 50% RATED THERMAL POWER when the Power Distribution System (PDMS) is inoperable and shall be performed:
- 1. Once per 7 days.
- 2. Once per shift when the NIS Power Range Tilts alarm is INOPERABLE as directed by 1BwOL 3.2.4 and 1BwOSR 0.1-1,2,3.
- 3. Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when QUADRANT POWER TILT RATIO is not within limits as directed by LCOAR IBwOL 3.2.4.
B. REFERENCES
- 1. Tech Spec LCO 3.2.4.
- 2. Tech Spec Surveillance Requirements:
- a. 3.2.4.1.
- b. 3.2.4.2.
- 3. TRM TLCO 3.3.h.
- 4. Station Procedures:
- a. 1BwOSR 0.1-1,2,3, Unit One MODES 1,2 & 3 Shiftly & Daily.
- b. 1BwOL 3.2.4, LCOAR - Power Distribution Limits - QPTR.
- c. 1BwOL TRM 3.3.h, Technical Requirements Manual (TRM) LCOAR Power Distribution Monitoring System (PDMS)
- d. BwVSR 3.2.4.2, QPTR Checkout Using Incores.
1
IBwOSR 3.2.4.1 Revision 2 Reference Use B. 5. Station Commitments:
- a. 456-200-87-38101, limitation to check the operability of the QPTR Alarm anytime QPTR exceeds 1.02.
- b. 456-130-98-3.2.4-0100 "Specific SAR Commitment" (Regarding shiftly surveillance interval when the power range tilts alarm is inoperable).
C. PREREQUISITES
- 1. Receive permission to perform this surveillance from the Shift Manager or designee prior to performance by having the Data Package Cover Sheet signed and dated.
- 2. Reactor power should be constant while recording NIS data.
- 3. The latest 100% Power NIS Detector Currents are available (from Station Nuclear Engineer or Operator Aid).
D. PRECAUTIONS None.
2
1BwOSR 3.2.4.1 Revision 2 Reference Use E. LIMITATIONS AND ACTIONS
- 1. As stated in Tech Spec LCO 3.2.4.
- 2. In the event the Acceptance Criteria (0) is not met during the performance of this surveillance, IMMEDIATELY notify the Shift Manager or designee to initiate
- LCOAR 18wOL 3.2.4.
- 3. Anytime the calculated QPTR exceeds 1.02, the NIS Power Range Tilts alarm OPERABILITY should be reviewed. If the alarm frequency of this surveillance shall be increased is not illuminated the required from once per7 days to once per shift in accordance with 1BwOL 3.2.4.
- 4. The process computer point calculation is the most accurate method of calculating QPTR and should normally be used.
During the performance of AFD calibrations on the excore detectors the process computer point method will not be correct until ALL drawers are calibrated.
During this calibration period QPTR MUST be calculated using the NIS meter method.
- 5. If the Power Range channel is inoperable but individual detector current indication is reliable, performance of BwVSR 3.2.4.2 is not required. Detector current indication can be considered reliable if detector degradation or failure is not indicated, the detector signal cable is attached proper high voltage is applied to the detector. to the 1PM07J drawer, and In this condition, the QPTR alarm may be inoperable but the neutron flux input to QPTR is available. QPTR can be calculated using the individual detector current meter indications.
3
1BwOSR 3.2.4.1 Revision 2 Reference Use F. MAIN BODY
- 1. VERIFY all applicable Prerequisites, Precautions, and Limitations and Actions are satisfactorily addressed.
- 2. INDICATE the applicability of this surveillance on the appropriate Data Sheet (REFER to Statement of Applicability):
- a. Being performed once per 7 days.
- b. Being performed once per shift.
- c. Being performed once per 12 hrs with BwVSR 3.2.4.2.
- d. Other (Specify).
- 3. RECORD the Date and Time.
NOTE With one Power Range Channel INOPERABLE POWER is > 50% but < 75%, the QPTR and THERMAL may be calculated using the three OPERABLE channels. With one to QPTR INOPERABLE with THERMALPower Range channel input POWER shall be calculated using the three OPERABLE > 75%, the QPTR channels taking data when directed by System Engineering during performance of BwVSR 3.2.4.2. RECORD "N/A" for the INOPERABLE Power Range channel data.
- 4. RECORD the OPERABILITY status and indicated Reactor Power from the NIS drawer front panel PERCENT FULL POWER meters on the appropriate Data Sheet.
4
1BwOSR 3.2.4.1 Revision 2 Reference Use NOTE Step F.5 and F.6 are independent of each other. Perform the applicable step.
Step F.5 will use the process computer to determine the QPTR.
Step F.6 will use installed NIS Meters or DVMs to determine QPTR.
F. 5. DETERMINE the QPTR using process computer points as follows (N/A if determined with the NIS meters):
- a. RECORD present computer point reading.
- b. DIVIDE the sum of the computer points by the number of operable channels to obtain the average computer point reading.
Average Computer Sum of Computer Points Point Reading = Number of Operable NIS Channels
- c. DIVIDE the Computer Point Reading by the Average Computer Point Reading to determine the Quadrant Power Tilt Ratio.
Power Tilt Ratio = Computer PointReadinq Average Computer Point Reading 5
1BwOSR 3.2.4.1 Revision 2 Reference Use F. 6.0 DETERMINE the QPTR usinq installed NIS Meters or DVMs NOTE Step 6.a will install DVMs, N/A step if using installed NIS Meters.
Step 6.b will determine the QPTR using installed NIS Meters or DVMs.
Step 6.c will remove DVMs, N/A step if using installed NIS Meters.
NOTE The following annunciator(s) may actuate during connection of the DVMs. This list is not all inclusive but if the annunciator(s) does not reset when the DVM is disconnected, investigate the cause before going to the next drawer.
1OA04PWR RNG UPPER DET FLUX DEV HIGH 1OB04PWR RNG LOWER DET FLUX DEV HIGH 1OC04PWR RNG CHANNEL DEV 1OB05PWR RNG FLUX HIGH ROD STOP To mCAUTION To minimize the effect of meter loading to the drawer, Fluke 8840A DVMs shall be used. If there are not enough 8840As available, Fluke 8505A and Fluke 8502 may be substituted. Other DVM may also be used with the consent of NIS System Engineer or backup. In addition, shielded test leads shall be used to avoid EMF induction to the reactor protection system circuitry.
A ReatoTipcolCAUTION WReactor Trip could occur if a 2 of 4 coincidence is A
made up due to a channel trip on the power range detector being measured. The DVM MUST be initially set to the millivolt range for detector current readings to prevent a channel trip.
If the current as seen on the face meter is low (at low powers), it is permissible to down range the detector meter current selector switch for better resolution.
6
1BwOSR 3.2.4.1 Revision 2 Reference Use EtCAUTION EutthD leads to be used have no flaws in their insulation. Also ensure that any contact points between the leads and the drawer are properly protected to ensure that chafing of the leads' insulation does. not occur. If the DVM leads become shorted to ground after connection, the associated power range channel will be made inoperable.
Pea b CAUTION Power range cables can become snagged while opening the drawers. Open the rear cabinet doors to 1PM07J and station a person at the rear of the drawers to ensure that all cables are free while opening the drawer.
Minimize motion of the cables, since the cable may become disconnected from its connector if excessive motion occurs. This could make the drawer inoperable.
F. 6. a. NOFITY IMD to perform the following for each Power Range "B" drawer:
- 1) CAREFULLY OPEN the Power Range Nuclear Instrumentation Channel "B drawer.
- 2) CONNECT a DVM between the red and black test jacks of the detector current meter for each of the eight Power Range detectors.
- 3) ROLL the Power Range "B" drawers carefully as far into the 1PM07J panel as possible. Avoid crimping or damaging the DVM leads. If possible, slightly engage the seismic screws on the front of the drawers.
7
1BwOSR 3.2.4.1 Revision 2 Reference Use F. 6. b. DETERMINE the QPTR using NIS meters or DVM as follows (N/A if determined with the computer points):
- 1) RECORD each present detector current.
- 2) RECORD the latest 100% Power NIS detector current (from the Station Nuclear Engineer or the Operator Aid).
- 3) DIVIDE the present detector current by the 100%
detector current to obtain the normalized detector current.
Normalized = Present Detector Current Detector Current 100% Detector Current
- 4) DIVIDE the sum of the normalized detector currents by the number of operable channels to obtain the average normalized current.
Average - Sum of Normalized Detector Currents Normalized Current Number of Operable NIS Channels
- 5) DIVIDE the Normalized Detector Current by the Average Normalized Current to determine the Quadrant Power Tilt Ratio.
Power Tilt Ratio = Normalized Detector Current Average Normalized Current 8
1BwOSR 3.2.4.1 Revision 2 Reference Use F. 6. c. PERFORM the following to RESTORE each Power Range "B" Drawers:
NOTE The following steps are applicable if DMVs are to be used to indicate detector current. Mark this section N/A if current meters. installed in the drawers are to be used.
CAUTION AW Power Range cables can become snagged while opening the drawers. Open the rear cabinet doors to 1PM07J and station a person at the rear of the drawers to ensure that all cables are free while opening the drawer. Minimize motion of the cables, since the cable may become disconnected from its connector if excessive motion occurs. This could make the drawer inoperable.
- 1) CAREFULLY OPEN the Power Range "B" drawers.
- 3) CAREFULLY CLOSE and SECURE the Power Range "B" drawers.
- 4) REMOVE all material installed to secure equipment.
G. ACCEPTANCE CRITERIA No Quadrant Power Tilt Ratio shall exceed 1.02.
(Final) 9
1BwOSR 3.2.4.1 Revision 2 Reference Use UNIT ONE QUADRANT POWER TILT RATIO CALCULATION COMPUTER POINTS The process computer point calculationNOTE is the most accurate QPTR and should normally be used. During the performancemethod of calculating on the excore detectors the process computer point method of AFD calibrations ALL drawers are calibrated. During this calibration period will not be correct until QPTR MUST be calculated using the NIS meter method.
Being performed once per:
o 7 Days (normal interval) Eo Shiftly o 12 Hours (with BwVSR 3.2.4.2) 0 Other:
ATTACH additional copies of this page as necessary.
D-2
1BwOSR 3.2.4.1 Revision 2 Reference Use UNIT ONE QUADRANT POWER TILT RATIO CALCULATION NIS METERS Being performed once per:
0 7 Days (normal interval) "o Shiftly o 12 Hours (with BwVSR 3.2.4.2) "O Other:
Date: Time:
Channel N41 N42 N43 N44 Is the channel indication reliable? OY ON OY ON OY ON QY ON Instrument reading % % % %
Upper Detectors (A)
Present upper detector current 100% upper detector current Normalized detector current Average normalized current Upper power tilt ratio (*1.02)
Lower Detectors (B)
Present lower detector current 100% lower detector current Normalized detector current Average normalized current Lower power tilt ratio (1 .02) ' 0 1 Date: Time:
Channel N41 N42 N43 N44 Is the channel indication reliable? nY 0ON OY ON 0 Y ON 1 Y ON Instrument reading % % % %
Upper Detectors (A)
Present upper detector current 100% upper detector current Normalized detector current Average normalized current Upper power tilt ratio (t1 .02)
Lower Detectors (B)
Present lower detector current 100% lower detector current Normalized detector current Average normalized current Lower power tilt ratio (0,01.02)
ATTACH additional copies of this page as necessary.
D-3
1BwOSR 3.2.4.1 Revision 2 Reference Use UNIT ONE DVM CALIBRATION TABLE Leads Installed IV Leads Removed Name/Date IV Name/Date Name/Date N41 To Name/Dma NamAflzasA Bottom I N42 T Bottom N43 To Bottom N44 To SBottom (Final)
D-4
JOB PERFORMANCE MEASURE TASK TITLE: Perform a QPTR Calculation JPM No.: N-18 REV: 10 TPO No.: IV.C.RK-01 K&A No.: (015A1.04)
TASK No.: RK-003 K&A IMP: 3.5/3.7 TRAINEE:
EVALUATOR:
DATE:
The Trainee: PASSED this JPM. TIME STARTED:
FAILED TIME FINISHED:
CRITICAL ELEMENTS: (*) 4, 9 JPM TIME: MINUTES CRITICAL TIME: NA APPROX COMPLETION TIME 17 MINUTES EVALUATION METHOD: LOCATION:
SPIN SIMULATE PLANT
- SIMULATOR GENERAL
REFERENCES:
- 1. 1BWOSR 3.2.4.1, Rev. 2, Unit One Quadrant Power Tilt Ratio (QPTR)
Calculation.
- 2. Operator Aid for 100% Power NIS Detector Currents.
MATERIALS:
- 1. 1BwOSR 3.2.4.1 (blank)
- 2. lBwOSR 3.2.4.1 page D-3, partially
- 3. completed. (Page 7 of this JPM).
Operator Aid for current values to be used in QPTR Calculation.
TASK STANDARDS:
- 1. Perform QPTR Surveillance (lBwOSR 3.2.4.1)
- 2. Demonstrates the use of good Core Work Practices (CWP).
TASK CONDITIONS:
- 1. You are an extra NSO.
- 2. The Unit 1 is at 100% power. PDMS is inoperable INITIATING CUES:
- 1. The US has provided you a copy of and directed you to perform the weekly QPTR calculation using lBwOSR 3.2.4.1.
The process computer is inoperable for the purpose of this surveillance.
Note to Examiner: Step 4 of this JPN requires data from the NIS meters and Op Aid.
data should be gathered before the This examinee starts this JPM. This data is to be compared to the data the examine, takes during the JPM to ensure he within + 10 uamps. is N-18 6/26/01 1
PERFORMANCE CHECKLIST STANDARDS SAT UNSAT N/A RBCORD START TI3X
- 1. Open and refer to lEwOSR Open and refer to the 03 03 0l 3.2.4.1, QPTR Calculation provided copy of 1BwOSR 3.2.4.1.
(CUB: All Prerequisites, VERIFY all applicable Precautions, Prerequisites, Limitations and Precautions, and Actions have been Limitations and Actions met.) are satisfactorily addressed.
- 2. Indicate the applicability Determine NIS meters must 03 03 []
of this surveillance on be used to perform this Data Sheet D-3. surveillance and INDICATE on Data Sheet D-3:
"* CHECK 7 day block.
"* RECORD current Date and Time.
- 3. Record power range NIs On Data Sheet D-3, RECORD 0 0 0 operability status. the following for power range NIs 41-44:
0 'Y' block checked for each channel (CuR, If asked, the Unit is indication reliable.
in No LCOARs at this time.) 0 100% (or present power reading from each channel at IPM07J).
- 4. Record each present All present Upper and detector current reading Lower Detector Currents from lPM07J on Data Sheet recorded within + 10 D-3. uamps of actual values on Data Sheet D-3.
UPPERS: E3 0 []
(Note: Prior to commencing this JPM, the actual "* N41 readings should be
"* N42 logged hare:
"* N43 UPPERS LOWERS
"* N44 N41 LOWERS:
N42 N43
"* N41 0 0 0 N44 "* N42 Log Op Aid Data here:
"* N43 N41
"* N44 N42 343 N44 2
N-18 6/26/01
PERFORMANCE CHECKLIST STANDARDS SAT UNSAT N/A Record the 100% Detector
- 5. Record 100% Detector Currents from the 0 03 0 Currents from Operator Aid Book on data Sheet D-3. Operator Aid Book for each upper and lower detector on Data Sheet D (CUN: If asked as the SUE 3:
for the values, "* Each upper report that they are in the operator aid "* Each Lower book.)
Note: After examines has recorded the data to this point from lPM07J, provide him/her with the partially filled in D-3 Data Sheet for calculations. (Page 7 of this JlW. Use the simulator setup instructions page 6 of this JPX for a 'KEY'.)
- 6. Using the partially filled Calculate the Normalized 0 0 0 in D-3 Data Sheet, perform Detector Currents for the calculations to obtain each detector by dividing the normalized detector its present detector currents and log them on current reading by the the data sheet. 100% detector current value from the operator aid and log on the D-3 Data Sheet:
"* Each Upper
"* Each Lower
- 7. Using the partially filled Calculate the Average Normalized Current by 0 0 0 in D-3 Data Sheet, perform the calculations to obtain summing the upper (lower) the average normalized normalized detector currents and log them on currents and dividing by the data sheet. 4 and log on the D-3 Data Sheet:
"* Upper Average
"* Lower Average
- 8. Using the partially filled Determine the QPTR for 03 03 0 in D-3 Data Sheet, perform each detector by dividing the calculations to each Normalized Detector determine the QPTR for Current by the Average each detector and log them Normalized Current and on the data sheet. log on the D-3 data sheet:
"* Each Upper
"* Each Lower
- 9. Identify N42 Upper Identify N42 Upper [] 03 03 Detector QPTR is Detector QPTR is >1.02 unacceptable. and is unacceptable.
Immediately notify the Shift Manager or Designee (CUR: As SM acknowledge the to initiate LCOAR lBwOL required initiation 3.2.4.
of LCOAR iBwOL 3.2.4.)
3 N-18 6/26/01
PERFORMANCE CHECKLIST STANDARDS SAT UNSAT N/A (CUR:) THIS COMPLETES THIS WXN.
RECORD STOP TIm COMMENTS:
4 N-18 6/26/01
JOB PERFORMANCE MEASURE TASK TITLE: Perform Quarterly Valve Stroke Surveillance of ICS007A PM No.: N-02CS007 REV: 0 TPO No.:
K&A No. 2.2.12 TASK No.:
K&A IMP: 3.0 TRAINEE:_
EVALUATOR:
DATE:
The Trainee: PASSED this JPM.
TIME STARTED:
FAILED TIME FINISHED:
CRITICAL ELEMENTS: (*)5-10 JPM TIME: MINUTES CRITICAL TIME: N/A APPROX COMPLETION TIME 14 MINUTES EVALUATION METHOD:
X PERFORM LOCATION:
IN PLANT SIMULATE X SIMULATOR GENERAL
REFERENCES:
- 1. 1BwOSR 3 . 6 . 3 .5.CS-1A Train A CS Containment Isolation Surveillance Valve Stroke Quarterly
- 2. Tech Spec 3.6.3 Containment Isolation
- 3. Tech Spec 3.6.6 Containment Spray Valves and Cooling Systems MATERIALS:
Copy of lBwOSR 3
.6.5.CS-IA Stop Watch TASK STANDARDS:
- 1. Perform 1BwOSR 3
.6.5.CS-lA, 1CS007A Valve Stroke Test TASK CONDITIONS:
- 1. You are the Extra NSO.
- 2. Unit 1 is in Mode 1, Unit 2 is in Mode 1 INITIATING CUES:
- 1. The Unit Supervisor has instructed you to perform 1BwOSR 3 .6.5.CS-1A, A Containment Spray Containment Train Surveillance for 1CS007A. The Isolation Valve Stroke Quarterly indication (1BwOSR 5.5.8.CS-2A)concurrent surveillance for position is not going to be performed at this time.
1
RECORD START TIME
- 1. Refer to IBwOSR 3.6.5.CS Locate and Open 1BwOSR 0 0 lA 3.6.5.CS-lA 0 (CUR: All prereqs, precautions, Review Prerequisites, limitations and actions Precautions, are met) Limitations and Actions (If asked) The surveillance cover sheet has been signed and approved by the US.
- 2. Review initial conditions Locate and review initial conditions, step 1 0 0 0 (CUR: The IST coordinator is Verify the IST listed on the Work coordinator is listed on Description Section for the Work Description results review) Section for review.
- 3. Record the stopwatch Data Record stopwatch data:
0 0 0 (CUR: Stopwatch data:
- Dept:
Dept: Ops If asked then the following: "o Accuracy Check Date:
Accuracy Check date:7/13/02 "o Due Date:
Due Date: 8/15/02
- 4. Record as found conditions Circle the as found (CUR: condition of listed 0 03 3 RK Suction pressure <75#
equipment:
"* 1SIO01A - NA
"* 1CS001A - OPEN
"* 1CS007A - CLOSED
"* 1A CS pump - STOP
"* 1A CS TEST - NORMAL
- 5. Ensure LOCAR 3.6.6 entered Enter LCO 3.6.6 for 1A CS Train when CS taken to 0 0 0 (CUE: LCO has been entered PTL for 1A CS Pump for Train A CS) 2 N-
PERFORMANCE CHECKLIST STANDARDS SAT UNSAT N/A
- 6. Take action to disable At lPM06J perform the Train A of CS from auto following: 0 0 0 actuations
"* Take C/S for lA CS pump to PTL
"* Verify 1A CS pump test switch in Normal
"* Close lA CS pump suction 1CS001A
- 7. Open 1CS007A and record Stroke and time ICS007A:
stroke time: 0 0 0
"* Place MCB C/S for 1CS007A to OPEN and simultaneously start the stopwatch.
"* Stop the stopwatch when 1CS007A indicates full open
"* Record stroke time in step 2.0 data table o Check status light
- 8. Close 1CS007A and record Stroke and time ICS007A:
stroke time: 0 0 0
"* Place MCB C/S for 1CS007A to CLOSE and simultaneously start the stopwatch.
"* Stop the stopwatch when ICS007A indicates full closed
"* Record stroke time in step 2.0 data table o Check Status Light
- 9. Identify that the stroke Record and review stroke time meets Tech Spec times on acceptance data 0 0 0 requirements sheet and verify acceptance criteria met.
3
PERFORMANCE CHECKLIST STANDARDS SAT UNSAT N/A
- 10. Restore system to 'as At lPM06J perform/verify found' condition. the following:
0 0 0
& 1A CS Pump STOP/NOT o ISIO01A N/A
"* ICS001A OPEN
"* 1CS007A CLOSED
"* 1CS01PA Test Switch NORMAL
RECORD STOP T33C __________
COMMENTS:
4
TASK CONDITIONS:
- 1. You are the Unit NSO.
- 2. Unit 1 is in Mode 1, Unit 2 is in Mode 1 INITIATING CUES:
- 1. The Unit Supervisor has instructed you to perform 1BWOSR 3 .6.5.CS-IA, A Containment Spray Containment Isolation Train Surveillance for lCS007A. The concurrent Valve Stroke Quarterly indication (lBwOSR 5.5.8.CS-2A) is surveillance for position not going to be performed at this time.
5 N-
SIMULATOR SETUP INSTRUCTIONS IPM NO: N-01CS007 REQUIRED SIMULATOR MODE(S): (any)
MALFUNCTION #'S: NA COMMENTS: Need stop watch from instructors booth 6
1BwOSR 3 .6.3.5.CS-1A Revision 1 Reference Use TRAIN A CONTAINMENT SPRAY CONTAINMENT ISOLATION VALVE STROKE QUARTERLY SURVEILLANCE A. STATEMENT OF APPLICABILITY The purpose of this procedure is to verify that 1CS007A strokes within the specified time when tested pursuant to Tech Specs 5.5.8, SR 3.6.3.5, and Bases T.3.6.3-1.
Testing will be performed at the interval of once per 92 days, or after any maintenance affecting valve operability and is applicable for MODES 1, 2, 3 and 4.
B. REFERENCES
- 1. Tech Spec LCOs:
- a. 3.6.6
- b. 3.6.3
- 2. Tech Spec Surveillance Requirement:
- a. 5.5.8
- b. SR 3.6.3.5
- 3. Station Procedures:
- a. BwAP 1900-1, Timepiece Accuracy Verification.
- b. 1BwOL 3.6.6, LCOAR - Containment Spray System.
- c. 1BwOL 3.6.3, LCOAR - Containment Isolation Valves.
- d. ER-AA-321, Admin Requirements for Inservice Testing.
- e. 1BwOSR 5.5.8.CS-2A, Containment Spray Power Operated Valve Indication 18 Month Surveillance.
- 4. Station Drawings: M-46
- 5. In Service Testing Program Plan for Pumps (IST Program)
- 6. NTS Item: 4 56
-100-93-01101C.
1
1BwOSR 3.6.3.5.CS-1A Revision 1 Reference Use C. PREREQUISITES
- 1. Receive permission to perform the surveillance from the Shift Manager or designee prior to performance by having the Data Package Cover sheet signed and dated.
- 2. This surveillance may be performed in any operating MODE.
- 3. A stopwatch wiN be necessary to perform this surveiltanoe,with timepiece accuracy verification per BwAP 1900-1.
D. PRECAUTIONS VERIFY that all requirements of the applicable RWP have been met.
E. LIMITATIONS AND ACTIONS
- 1. As stated in Tech Spec LCOs 3.6.6 and 3.6.3.
- 2. In the event a valve fails to change position, or the stroke time exceeds the Operability (Oper) Limit during surveillance performance, IMMEDIATELY NOTIFY the Shift Manager or designee to declare the valve inoperable and initiate corrective actions.
- 3. In the event a valve stroke time exceeds the Alert Limit, but is less than the Operability (Oper) Limit, the following should be performed:
- a. The Shift Manager or designee must be notified.
- b. The valve should be stroked a second time.
- c. NOTIFY the System Engineer to PERFORM an evaluation to document valve operability (per ER-AA-321) and attach it to this surveillance.
- d. If the second stroke time exceeds the Alert Limit, but is less than the Operability (Oper) Limit, then the valve must be tracked with a 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> time clock to decide the ER-AA-321 operability determination. (N/A if second stroke is within Alert Limits.) (Valve is considered operable until evaluation is complete.) (The Dequip program is an acceptable tracking method.)
2
1BwOSR 3.6.3.5.CS-1A Revision 1 Reference Use E. 4. For any valve declared inoperable demonstrate acceptable operation after required corrective action has been taken but before returning the valve to service.
- 5. IF ALARA concerns permit, THEN local stroke timing and local examination of the valve should be performed if Operability Acceptance Criteria (Oper Limit) is not met.
.6.: -Per the.requirements of the IST Program Tech .Spec 5.5.8, valve stroke time limits SHALL be set up which accurately reflect the way the valve strokes. These times, in some instances, may be more limiting than other Tech Spec values.
Per the IST Program requirements Tech Spec 5.5.8, these stroke times SHALL be the basis on which the valve is declared inoperable.
- 7. When the CS Pump CONTROL Switch is placed to PULL TO LOCK, NOTIFY Shift Manager or designee to initiate LCOAR the 1BwOL 3.6.6.
- 8. PERFORM 1BwOSR 5.5.8.CS-2A concurrently if possible, to obtain both stroke time data and indication checks.
3
1BwOSR 3.6.3.5.CS-1A Revision 1 Reference Use F. MAIN BODY 0.0 SURVEILLANCE OVERVIEW 0.1 The timing valve strokes may be performed in any order to minimize the number of needless valve strokes.
0.2 The subsections of this surveillance perform the following.
F.1 .0 Establish Initial Conditions F.2.0 Stroke Test of 1CS007A 4
1BwOSR 3.6.3.5.CS-1A Revision 1 Reference Use I ! t-F. 1.0 INITIAL CONDITIONS NOTE Initial each step in the space provided adjacent to the procedure step number AFTER the step has been SUCCESSFULLY completed.
I Person(s) performing VERIFICATIONS SHALL initial in the space provided following the step.
NOTE
'Valve stroke time" is defined as the time duration from the instant of handswitch (or manual relay) actuation until the instant of indication of the valve's intended final position.
1.1 VERIFY all applicable PREREQUISITES, PRECAUTIONS, and LIMITATIONS and ACTIONS satisfactorily addressed.
1.2 VERIFY the IST Coordinator is listed in the Work Description Section of the Data Package Cover Sheet to review the results.
1.3 RECORD the Stopwatch data.
Dept/No.:
Accuracy Check Date:
Due Date:
NOTE The As Found Position of 1SI001A may be marked N/A if RH Suction Press is less than 75 psig.
1.4 RECORD the "As Found" position of the following:
1 1SI100A, 1A CS Pmp Disc Test Line to RWST OPEN/LOCKED/CLOSED/NA
- 1CS001A, Cnmt Spray Pump 1A RWST Suction VIv OPEN/CLOSED
- 1CS007A, Cnmt Spray Pump 1A Header Isol VIv OPEN/CLOSED
- 1CS01PA, Cnmt Spray Pump 1A RUN/STOP/PTL
- 1CSO1PA TEST SWITCH, Cnmt Spray Pump 1A Test Switch NORMAL/TEST 5
1BwOSR 3.6.3.5.CS-1A Revision 1 Reference Use F. 2.0 STROKE TEST OF 1CS007A Valve: 1CS007A Panel: 1PM06J Stroke @ Oper @ Alert Status @ Test @ Retest Ver Oper Init Stroke__ .Limits
- Limits
- Lights Time Time 0_,,_Time OPEN Maxl1 M65 OLIT O YES OE MDARK 10 NO Min 6.5 O]LIT OVlES NES CLOSE Max 13.1 IMax Max 10. DAR 10.9 0[] DARK 10 0 NO 2.1 VERIFY/PLACE the 1A CS Pump handswitch in PULL TO LOCK at 1PM06J.
2.2 VERIFY/PLACE 1CS01PA Test Switch in the NORMAL position at 1PM06J.
NOTE I Step 2.3 is N/A if RH Suct Press is less than 75 psig.
2.3 UNLOCK and OPEN ISI001A, 1A CS Pump Dsch Test Line to RWST.
2.4 VERIFY/CLOSE ICS001A at 1PM06J.
2.5 Use the handswitch at 1PM06J to STROKE 1CS007A in the OPEN direction.
(PERFORM in accordance with steps outlined in ATTACHMENT A, Timing in the OPEN Direction.)
2.6 Use the handswitch at 1PM06J to STROKE 1CS007A in the CLOSE direction.
(PERFORM in accordance with steps outlined in ATTACHMENT B, Timing in the CLOSE Direction.)
2.7 OPEN 1CSOO1A at 1PM06J.
@ All limits and times are in seconds.
6
1BwOSR 3.6.3.5.CS-1A Revision 1 Reference Use NOTE If step 2.3 was not performed, the As Left position of 1SI001A may be marked N/A.
F. 2.8 RESTORE the following equipment to the "As Found" position or as directed by the Shift Manager or designee.
- 1CSO1PA, Cnmt Spray Pump 1A RUN/STOP/PTL VERIFICATION 0 1SIO01A, 1A CS Pmp Disc. Test Line to RWST OPEN/LOCKED/CLOSED/NA VERIFICATION
- 1CS001A, Cnmt Spray Pump 1A RWST Suction Valve OPEN/CLOSED VERIFICATION
- 1CS007A, Cnmt Spray Pump 1A Header Isolation Valve OPEN/CLOSED VERIFICATION 0 1CS01PA Test Switch, Cnmt Spray Pump IA Test Switch NORMAL/TEST VERIFICATION 7
1BwOSR 3.6.3.5.CS-1A Revision 1 Reference Use G. ACCEPTANCE CRITERIA
- 1. Each valve must have been verified to stroke within the Operability (OPER)
Limits.
- 2. Each valve must have been verified in accordance with one of the following:
a.- The valve stroke time was within the Alert Limits.
- b. The valve stroke time exceeded the Alert Limits, but was within the Operability (Oper) Limits and the following criteria have been met:
- 1) The valve was stroked a second time.
- 2) ER-AA-321, is attached to this surveillance for the System Engineer to evaluate.
- 3) The second valve stroke time exceeded the Alert Limits, but was within the Operability (Oper) Limits and the valve is being tracked with a 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> clock to complete the ER-AA-321 evaluation. (Valve is considered operable until evaluation is complete.) (The Dequip program is an acceptable tracking method.)
8
1BwOSR 3.6.3.5.CS-1A Revision 1 Reference Use ATTACHMENT A TIMING IN THE OPEN DIRECTION
- 1. VERIFY/CLOSE the valve.
- 2. SIMULTANEOUSLY START the stopwatch and OPEN the valve with the test switch.
- 3. STOP the stopwatch when the valve indicates OPEN.
- 4. RECORD the stroke OPEN TEST TIME.
- 5. RECORD the MLB status light indication associated with the valve.
- 6. VERIFY the valve indicates OPEN on the control panel.
- 7. VERIFY the OPEN TEST TIME is within the OPERABILITY (OPER) LIMITS. (If not, DECLARE the valve INOPERABLE and initiate appropriate actions.)
- 8. If the valve is within the OPERABILITY (OPER) LIMITS, but is not within ALERT LIMITS, PERFORM the following (otherwise N/A):
- a. VERIFY/CLOSE the valve (May be performed in conjunction with a close stroke timing step).
- b. SIMULTANEOUSLY START the stopwatch and OPEN the valve with the appropriate test switch(es).
- c. STOP the stopwatch when the valve indicates OPEN.
- d. RECORD the stroke OPEN RETEST TIME.
- e. VERIFY the OPEN RETEST TIME is within the OPERABILITY (OPER) LIMITS.
(If not, DECLARE the valve INOPERABLE and initiate appropriate actions.)
- f. Attach ER-AA-321, to this surveillance for the System Test Engineer to evaluate.
- g. If the second stroke time exceeds the Alert Limit, but is less than the Operability (Oper) Limit, then TRACK the valve with a 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> clock to complete the ER-AA-321 evaluation. (Valve is considered operable until evaluation is complete.)
9
1BwOSR 3.6.3.5.CS-1A Revision 1 Reference Use ATTACHMENT B TIMING IN THE CLOSE DIRECTION
- 1. VERIFY/OPEN the valve.
- 2. SIMULTANEOUSLY START the stopwatch and CLOSE the valve with the test switch.
- 3. STOP the stopwatch when the valve indicates CLOSED.
- 4. RECORD the stroke CLOSED TEST TIME.
- 5. RECORD the MLB status light indication associated with the valve.
- 6. VERIFY the valve indicates CLOSED on the control panel.
- 7. VERIFY the CLOSED TEST TIME is within the OPERABILITY (OPER) LIMITS. (If not, DECLARE the valve INOPERABLE and initiate appropriate actions.)
- 8. If the valve is within the OPERABILITY (OPER)'
LIMITS, but is not within ALERT LIMITS, PERFORM the following (otherwise N/A):
- a. VERIFY/OPEN the valve (May be performed in conjunction with an open stroke timing step).
- b. SIMULTANEOUSLY START the stopwatch and CLOSE the valve with the appropriate test switch(es).
- c. STOP the stopwatch when the valve indicates CLOSED.
- d. RECORD the CLOSED RETEST TIME.
- e. VERIFY the CLOSED RETEST TIME is within the OPERABILITY (OPER)
LIMITS. (If not, DECLARE the valve INOPERABLE and initiate appropriate actions.)
- f. Attach ER-AA-321, to this surveillance for the System Test Engineer to evaluate.
- g. If the second stroke time exceeds the Alert Limit, but is less than the Operability (Oper) Limit, then TRACK the valve with a 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> clock to complete the ER-AA-321 evaluation. (Valve is considered'operable until evaluation is complete.)
(Final) 10
JOB PERFORMANCE MEASURE TASK TITLE: Prepare/Perform a Liquid Radwaste Release JPM No.: N-32 REV: 12 TPO No.: IV.C.WQ-01 K&A No.: (068A4.02)
TASK No.: WX-002 K&A IMP: 3.2/3.1 TRAINEE:
EVALUATOR: DATE:
The Trainee: PASSED this JPM. TIME STARTED:
FAILED TIME FINISHED:
CRITICAL ELEMENTS: (*) 5-7 JPM TIME: MINUTES CRITICAL TIME: NA APPROX COMPLETION TIME: 16 MINUTES EVALUATION METHOD: LOCATION:
X PERFORM IN PLANT SIMULATE X SIMULATOR GENERAL
REFERENCES:
- 1. BwOP WX-501T1 Rev. 19, Liquid Release Tank OWX01T Release Form MATERIALS:
Copy of BwOP WX-501T1, Liquid Release Tank OWX01T Release Form completed through section D.
TASK STANDARDS:
- 1. Complete Section E of a liquid release tank release form in accordance with BwOP WX-501T1.
- 2. Correctly operate the RM-11 for setpoint adjustment/testing.
- 3. Demonstrates the use of good Core Work Practices.
TASK CONDITIONS:
- 1. You are an extra NSO.
- 2. Both Units are at 100% power.
- 3. OPR01J, OPRIOJ, and OUR-CW032 are operable.
- 4. All Channel Checks are complete.
INITIATING CUES:
- 1. The Unit Supervisor has handed you an OWX01T liquid release package, completed through section D, and has directed you to complete the release package through Section E, using the HIGH flowrate path.
N-32(7/14/01)
PERFORMANCE CHECKLIST STANDARDS SAT UNSAT N/A RECORD START TINE Note: Provide the examines with a copy of BwOP WX-501TI completed through Section D, page
- 18. Provide cues to the examine* only if actual equipment is unavailable. When requested
".y the examines, Independent Verification has been completed.
- 1. Indicate the release flow Indicate the release flow 0 0 0 path as HIGH FLOW, by path as HIGH FLOW by circling on the form. circling on the release form.
(Note: HIGH Flow Rate was given as an initiating cue.) I -
- 2. Obtain and record the High Obtain and record the 0 10 0 Alarm and Alert Alarm High Alarm and Alert Setpoints for ORE-PRO10 Alarm Setpoints for ORE from the RM-II. PR010 from the RM-11 as follows:
"* DEPRESS Grid 1 key.
"* Key in ýii00.
"* DEPRESS SEL key.
"* DEPRESS CHAN ITEMS key.
(Chan Item #9 "* RH0RD Chan Item #9, High Alarm Setpoint.
(Chan-Ianem #20 .....- )
"* RECORD Chan Iten* #10, Alert Alarm Setpoint.
- 3. Obtain and record the High Obtain and record the 0 0 03 Alarm and Alert Alarm High Alarm and Alert Setpoints for ORE-PRO01 Alarm Setpoints for ORE from the RM-1. PRO01 from the RM-11 as follows:
"* DEPRESS Grid 1 key.
"* Key in "1010.
"* DEPRESS SEL key.
"* DEPRESS CHAN ITEMS key.
(Chan Item #9
- RECORD Chan Item #9, High Alarm Setpoint.
- RECORD Chan Item #10, (Chan Item #10 Alert Alarm Setpoint.
2 N-32 (7/14/01)
PERFORMANCE CHECKLIST STANDARDS SAT UNSAT N/A
- 4. Verify OBwOSR 0.1-0 daily Check rounds to ensure 0 0 0 channel check is complete OBwOS 0.1-0 daily on Liquid Radwaste channel check Effluent monitor (ORE surveillance is complete PRO01), Station Blowdown on the following:
Monitor (ORE-PRO10), and Station Blowdown Line "* ORE-PRO01 Liquid Monitor Loop (0-CW032). Radwaste Effluent.
"* ORE-PR010 Station (CUm: As examine. asks for Blowdown.
status of surveillances, report "* 0-CW032 Station they are all Blowdown Line Monitor completed BAT as of Loop. I shift 1 today.)
- 5. Perform lineup in Contact Radwaste to 0 0 0]
preparation to verify prepare to verify 0AOV valve OAOV-WX353 auto WX353 Auto closes on high closes on high radiation. radiation as follows:
(CUR: An asked, sufficient o VERIFY sufficient blowdown flow is blowdown flow is established; established.
WX-302 and 890 are "* VERIFY/CLOSE OAOV CLOSND; WX302.
"* VERIFY/CLOSE OAOV WX890.
WX889 is OPENI "* VERIFY/OPEN 0AOV WX889.
Release Tank Pump is "* VERIFY/START OWX01P, runningi Release Tank pump.
The discharge hdr hi o VERIFY/CLEAR Release rad alarm is clear; Tank Discharge Header Radiation High annunciator.
OAOV-WX353 is OPim OPEN OAOV-WX353 using using the key.) the key obtained from the OPS Supervisor or SM.
3 N-32 (7/14/01)
PERFORMANCE CHECKLIST STANDARDS SAT UNSAT
- 6. Verify the Auto Closure of N/A Verify the Auto Closure the release tank discharge of OAOV-WX353 by LOWERING 3 0 0 isolation valve 0AOV the liquid radwaste WX353. effluent monitor ORE PRO01 High alarm setpoint to a value below the current activity level as follows:
"* PLACE the RM-I1 console in the SUPERVISOR mode.
" SELECT the HIGH alarm setpoint (channel item
- 9) to be changed on ORE-PRO01 (OPSI01)
CHAN ITEMS by keying in 9 and DEPRESSING the SEL key.
(Current activity setting ) 0 Record the current activity reading.
ENTER a new HIGH alarm setpoint below the current activity value.
(Now Hi Alarm setting____
o RECORD the new HIGH alarm setpoint that was entered.
- DEPRESS the ENTER key.
o ACKNOWLEDGE the alarm at the RM-li console.
Contact the local operator to: 0 0 0 (CUB:
- VERIFY OAOV-WX353 AUTO When contacted report CLOSES.
OAOV-WX353 Auto Closed, o VERIFY Release Tank The high rad alarm discharge Header annunciated, Radiation High alarm annunciates.
- PLACE key locked and (when directed) switch for OAOV-WX353 the key locked switch in CLOSE.
for OAOV-WX353 is in CLOSE.)
4 N-32 (7/14/01)
PERFORMANCE CHECKLIST STANDARDS SAT UNSAT N/A
- 7. VERIFY/ADJUST the Alert VERIFY/ADJUST the ALERT 03 03 0 and High alarm setpoints alarm and HIGH alarm for ORE-PR001 to the setpoints to the values values specified by Health specified by Health Physics is step D.7.b. Physics in step D.7.b as follows:
"* PLACE the RM-11 Console in the SUPERVISOR mode.
" SELECT the ALERT alarm setpoint (channel item
- 10) to be changed on the ORE-PRO01 (OPS101)
CHAN ITEMS display by KEYING in 10 and DEPRESSING the SEL key.
" ENTER the new ALERT alarm setpoint (656-5) and DEPRESS the ENTER key. (3.193-4)
" SELECT the HIGH alarm setpoint (channel item
- 9) to be changed on the ORE-PR001 (OPSI01)
CHAN ITEMS display by KEYING in 9 and DEPRESSING the SEL key.
" ENTER the new HIGH alarm setpoint (131-4) and DEPRESS the ENTER (CUB: When asked, key. (6.382-4)
Independent Verification is o INDEPENDENT complete.) VERIFICATION obtained.
- 8. Contact the radwaste Contact the radwaste 0 0 0 operator and VERIFY/CLEAR operator and VERIFY/CLEAR Release Tank Discharge Release Tank Discharge Header Radiation High Header Radiation High annunciator. annunciator.
- Window 77A09 at OPL01J.
(CUB: When asked, Release Tank Discharge Header Radiation High annunciator is clear.)
5 N-32 (7/14/01)
PERFORMANCE CHECKLIST STANDARDS SAT
- 9. VERIFY/ADJUST the ALERT UNSAT N/A VERIFY/ADJUST the ALERT and HIGH setpoints for alarm and HIGH alarm 3 0 0 ORE-PRO10 to the values setpoints to the values specified by Health specified by Health Physics is step D.8.b. Physics in step D.8.b as follows:
(Note: This step is NOT SELECT the ALERT alarm required (because setpoint (channel item there were no changes #10) to be changed on to these setpoints), the ORE-PR010 (OPS110) but is included here CHAN ITEMS display by in case the examinee KEYING in 10 and performs it anyway.) DEPRESSING the SEL key.
" ENTER the new ALERT alarm setpoint (573-6) and DEPRESS the ENTER key. (5.803--6)
"* SELECT the HIGH alarm setpoint (channel item
- 9) to be changed on the ORE-PRO10 (OPSI10)
CHAN ITEMS display by KEYING in 9 and DEPRESSING the SEL key.
" ENTER the new HIGH alarm setpoint (819-6) and DEPRESS the ENTER key. (1.203-5)
(CUB: When asked, " PLACE the RM-11 IND3PENDNT console in the NORMAL VERIFICATION is mode.
complete.) " INDEPENDENT VERIFICATION obtained.
- 10. Record Circulating Water Obtain/Record the Blowdown rate and obtain following: 0 0 0 verifications.
- Circ Water Blowdown rate from OUR-CW032 at OPM01J, or computer point F2400.
- SUPERVISOR (CUB- When asked for VERIFICATION.
verificationse/ "* VERIFY CW blowdown reviews, they are rate > 8000 gpm.
complete.) "* Control Room Supervisor Review.
(CUE:) THIS COMPLETES THIS jpM.
RECORD STOP TIME___ _______
COMMENTS:
6 N -32 (7 /14,/ 0 1)
TASK CONDITIONS:
- 1. You are an extra NSO.
- 2. Both Units are at 100V power.
- 3. OPR01J, OPR1OJ, and OUR-CW032 are operable.
- 4. All Channel Checks are complete.
INITIATING CUES:
- 1. The Unit Supervisor has handed you an OWX01T liquid release package, completed through section D, and has directed you to complete the release package through Section E, using the HIGH flowrate path.
N-32(7/14/01)
SIMULATOR SETUP INSTRUCTIONS 3PM NO: N-32 REQUIRED SIMULATOR MODE(S): ANY MALFUNCTION #'S: N/A COMMENTS:
- 1) BwOP WX-501T1 needs to be filled out through section D.
- 2) Verify/Start OWX01P on SDG WD5 (RF WD12 ON).
- 3) if contacted as radwaste operator, report:
-adequate blowdown flow
-0WX353 is CLOSED
-0WX890 is CLOSED
-0WX389 is OPEN
-Release Tank pump is started
-Release Tank discharge Header Rad High annun is CLEAR.
- 4) When contacted as radwaste operator, report 0WX353 is OPEN.
- 5) When contacted as radwaste operator, report 0WX353 is CLOSED.
- 6) When contacted as RWO, report the Release Hdr Rad High Alarm is in and has been acknowledged.
- 7) When contacted as RWO, report the high rad alarm is CLEAR.
8 N-32 (7/14/01)
BwOP WX-501T1 Revision 19 Continuous Use LIQUID RELEASE TANK 0WX01T RELEASE FORM Release Number L -
-k OPERATING DEPATMENT RESPONSIBILITY-RADWASTE OPERATO NOTE Desired level is 85% to 90% for Release Packip nintaion, y, however, a Release Package may be initiated anytime OWX01T level is_> 50%. The mixer should not be run when level Is < 70%.
Consideration should be given future water management needs when initiating a package with level < 85%.
VERIFY 0WX01T Is Redrculating per BwOP WX-171. .
.1 I ", -,
Tank Redrculation Started Date Time
-c2 RECORD 0WX01T Tank Level. .;'=
0WX01T Tank Level
-~-3. COMPLETE the entrles in the Uquld Release Log in the RWCR.
NOTE If a release is in progress for tank OWX26T, Step A.4., It may be marked "N/A'. It Is checked again In Section D.
if 0PR01 J is NOTj required for sampling of 0WX26T, VERIFY that the 0PR01 J return Is lined up to 0WX01T by performing the following valve lineup:
- a. VERIFY/OPEN "NO EPN", OPRO1J return to 0WX01T.
- b. VERIFY/CLOSE "NO EPN', OPROIJ return to 0WX26T.
_L5. RECORD the Release Number from the Liquid Release Log in the space provided on page 1.
1
BwOP WX-501T1 Revision 19 Continuous Use NOTE The minimum mixing time required for an accurate sample is
§ minutes, if redrculating with the mixer ON or §0 minutes, N recirculating with the mixer OFF. After meeting time requirements, Chemistry can be called for a sample.
A,6. WHEN the minimum mixing time requirements have, been satisfied. NOTIFY Chemistry that a Release Package in progress requires 0WXOIT sampling.
NOTE If more than 25% of the volume In the Release Tank is water that was drained or processed out of one or more systems to support Refueling or Forced Outage activities, it is "Outage Water.
Is the water in this tank considered to be outage water?
IHYES O NO
- -8. Is OWX01T level greater than 80% (From Step A.2.)?
"*, YES (GO TO STEP A-9.) 0 NO (MARK STEP A.9. -N/A7.)
NOTE Ifmore than 55 gallons of caustic has accumulated at the Release Tank Chemical Addition area (426' by 1A FW Pp), a caustic add should be performed unless directed otherwise by the Shift Supervisor based on release priorty.
Is it desired to add caustic to 0WX01T?
ý9-D YES %KNO VERIFY/DELIVER this release package to the non-outage Unit Supervisor.
I ý10.
2
BwOP WX-5O1TI Revision 19 Continuous Use B. OPERATING DEPARTMENT RESPONSIBILITY - UNIT SUPERVISOR NOTE Kankakee River Flow rate is normally obtained via the Internet site for the US ARMY CORPS OF ENGINEERS, WILMINGTON DATA (from the appropriate Unit Supervisor). If data Is unavailable, RECORD most recent data from the Unit Supervisor turnover.
~-1. OBTAIN and RECORD current (within the last 24 hrs.) Kankakee River flow data:
Stream Flow. TSeW CFS at Date: at rime: a
~2. RECORD the START AFTER time from BwOP WX-501T2, Release Time Table, for the flow rate recorded In Step B.1.
Release can start after I10" NOTE A TSS analysis Is required on &L tanks released on the first day of the sampling week. that releases am paermed. The first release tank of the month requires Oil and Grease analysis. These sample analysis add 4-5 hours to the processing time. All chemistry analysis calculations require second verification (If there Is only one Chem Tech Available, the verification occurs the following shift). A release package can process through Chemistry In as little as three hours If there are two Chem Techs, there are no higher priorities, no caustic add Is required, and OPR01J is operable.
EVALUATE the expected time of release so that both biocide treatment and the t_ 3. release can be accommodated considering:
"* CW Biocide treatment requires associated Unit CW blowdown isolated.
"* At least 8000 GPM CW blowdown flow is required for the Liquid release.
RECORD the Kankakee River flow rate obtained in step B.1. in the Unit
- 4. Supervisor Turnover.
3
BwOP WX-501T1 Revision 19 Continuous Use B. 5. AAR OBwOS RETS 2.1-la in effect for:
S* ORE-PROOl 0 YES 4 NO VERIFICATION SORE-PROlO 0 YES. )(NO NOTE Prior to forwarding this Release Package to the Chemistry Department. Step E.I. and E.2. may be perforned if operating condrions penmt.
- 6. OPS Supedsqr.o I have reviewed Parts A and B and have verified them acctrate OPS~r6pem"~o "Date Time NOTIFY the RADWASTE OPERATOR that his release package is ready for prompt delivery to Chemistry.
t- 7.
4
BwOP WX-501T1 Revision 19 Continuous Use C. CHEMISTRY DEPARTMENT RESPONSIBILITY NOTE 100% level for the 0WXO1T release tank is 32.900 gallons.
NOTE IfORE-PROO1 is inoperable under AAR OBwOS RETS 2.1-1a, analyses other than isotopic required in this package, i.e., Tritium, Boron, O & G (if required), and TSS (if required) must be run and the numbers reported on one of two samples that meet the 30%
acceptance criteria.
- 1. To verify a request has been made to add caustic to OWXO1T Release Tank,,
verify. yes applies to all statements specified in step A.8 and A.9. . . ,;
o All statements are yes, a chemical addition has been requested, proceed to step C.2.
0 Not all statements apply. A chemical addition will not be performed, proceed to step C.3.
- 2. Caustic addition to OWXOIT.
- a. Sample and analyze OWXO1T for boron concentration.
Sampled by Time/Date Results AIA- ppm (Record boron value in step C.9).
- b. Submit a chemical addition using BwCP 340-1T4 for caustic to OWXO1T based on the following chart.
- 200 0
>200* 600 :5
>600* 1000 *10
>1000:51500 515
>1500 *520 5
BwOP WX-501 TI Revision 19 Continuous Use C. 2. C. submitted by
. Proceed to step C.2.d.
be added based on boron by Chem Tech Proceed to step C.3.
- d. Alter receiving notification that,the caustic on to OWX)OIT Is complete proceed to step C.3.
Tlme/Date notified that add was completed .. _ __"__
- 3. Sampling.the Release Tank Effluent "NOTE After obtaining a sample of the Release Tank, the analysis listed in Section C (Excluding sections C.A and C.2). can be performed in any order necessary to perform the analysis in a saee and timely fashion. It Is not necessary to complete one analysis before starting another. The sequence of performing the analysis is left to the discretion of individual performing the tasks.
1st Set 2nd Set (If Required) 1st Sample 2nd Sample 1st Sample 2nd Sample (If Required) (if Required)
Sampled by _ _ _ _
Date "*OA-4 Sample Time -400
- a. One liter in a poly bottle for isotopic analysis (per BwCP 210-11), tritium analysis (per BwCP 220-2), boron analysis (per BwCP 103-10) and 250 ml for the "monthly save" (monthly composites).
- b. For the first release package of the month, analyze for Oil and Grease analysis as directed per BwCP 323-18.
6
BwOP WX-501T1 Revision 19 Continuous Use NOTE Additional release packages sampled on the same day as those analyzed in Step C.3.c. will require TSS samples also.
C. 3. c. For the day of the first release package of the week, "ain a sample for Total Suspended Solids (TSS) analysis for L releses as directed per BwCP 323-18.
- 4. ISOTOPIC SAMPLING CHECK
- a. If Radwaste Effluent Process Monitor, ORE-PR001 ij operable per AAR OBwOS RETS 2.1-1a (see Step B.5.) then N/A Step C.5.
- b. If Radwastq Effkmnt Process Monitor, ORE-PR001 ig not operabe per AAR 0BwOS RETS 2.'1-ia (see Step B.5.) then perform Step C.5.
S..... is to.IN NOTE If an Isotopic VqerifcatiOn perfNormed then an independent sample of sufficient volume for.an Isotopic must be taken by an, Independent qualified individual. Fill in Table on page 6.
I N _-5. ISOTOPIC VERIFICATION
- a. VERIFY that Cobalt 58 (Co-58) activities, obtained from the Weighted Mean Decay Corrected Table, are within 2Q% of each other by performing the following calculation:
A/B< 1.30 Where:
A = The Larger Co-58 activity, iCi/g =
B = The Smaller Co-58 activity, jCi/g =
A/B =
Ifthe activities are within 30% of each other, N/A Steps C.5.b. through C.5.f. and proceed to Step C.6.
7
BwOP WX-501T1 Revision 19 Continuous Use C b. If the activities were not within 2Q% of each other, perform the following:
- 2) INFORM OPS Supervision.
- 3) OBTAIN another set of INDEPENDENT samples.
- 4) PERFORM an isotopic analysis on each of the second set of samples.
- 5) VERIFY that Cobalt 58 (Co-58) activites, Weighted Mean Decay Corrected Table, obtained from the are within 30% of each other by performing the following calculation:
NBl3Q Where:
A = The, Larger Co-, activity, Cig =
B = The Smaller Co-58 activity,
=Ci/g =_
A/B = _____
C. A second INDEPENDENT set of samples has been obtained, analyzed and the Co-58 activities verified to be within IQ% of each other.
o YES, PROCEED to Step C.6.
o NO, INFORM OPS Supervision and Chemistry Supervision immediately. Save other analysis results, i.e., Tritium, boron, 0 & G (if required) and TSS (if required) obtained on the second set of samples.
Signature Date 8
BwOP WX-501T1 Revision 19 Continuous Use Chemistry and OPS SupervisionNOTE will attempt to resolve the activity may be necessary Radiation Protection Supervision may need be consulted to re-evaluate the to 2Q% acceptance criteria.
- 5. d. Radiation Protection has waived 30% acceptance criteria.
Rad. Protection Supervisor Date Time OPS Supervisor Date Time
- e. if Radiaon Protection waives the IQ% acceptance criteria, report results for Tritium, boron, 0 & analysis G
obtained on the second set of samples.(if requLired) and TSS (if required)
- f. If Radiation'P ecfndoes not waive discard analysis results fo Tritium, dw 2Q% acepw crtra required) obtained on the second boron, 0 & G (if required) and TSS (if that this pacag is term-inated set of samples. Notify OPS Supervisor and return to hm. Chemistry Supervision will begin an investigation to determine the difference.
_.6. Radionuclide Analysis Performed (Isotopic report(s) attached)
- 3__7. ANALYZE sample for tritium per BwCP 220-2, and RECORD the results from the completed BwCP 220-2T1.
PARA!METERR FREQUENCY LIMIT 8.
Tritium Each Batch I NoeL!Cv RESULTS I
Composite sample drawn, labeled with sample time, date and assigned number and placed in designated release sample storage area.
- 9. ANALYZE sample for boron concentration, IS per BwCP 103-10 and RECORD if not previously obtained in step the results below. C.2.
FREQUENCY P T DILUTION ANK DISCHARGE LIMIT C Boron Batch IPPMo2 1 Cm NCNTR A-TION TpmON 9
BwOP WX-501T1 "Revision19 Continuous Use
- 10. Maximum Discharge Rate based on Water Quality Chemical Analysis PERFORM the following calculation for each analysis:
A = MAXIMUM DISCHARGE RATE C (gpm)
A = Kankakee River Flowrate = 9 gpm.
B = Parnmeter Limit = I ppm C = Tank Concentration (from Step C.9.)
Maximum Discharge Rate
-S / gpm (not to exceed 500 gpm)
NOTE All E£ggired NPDES LIMITS mnust be satisfied in the release tank I
M L91.ANALYZE samp~le as required by the NPDES Permt for Total per CY-AA-130-9140W Suspended
. Oi and Grease per BwCP 100-10: Solis" results from the complted appropriate RECORD the '
T-sheets below and on BwCP 323-18T1.
N/A this Step if NPDES sampling has been saisfied.
PARAMETER FREQUENCY LIMIT RESULTS ota Sus nded Solids Per Current NPDES Permi.__t m m Oil and Grease er Current NPDES Permit M m 10
BwOP WX-501T1 Revision 19 Continuous Use C. 12. Is the Release Tank within all specified NPDES limits as deterrined in step C.11?
3 YES a. The release tank is approved for Chemical Release.
- b. Perform Step C. 13.. then forward this procedure Health Physics Department or back to to the the Operating Deatfnent for Step E.1.
Li NO a. IMMEDIATELY NOTIFY the OPSSupervisor OPS Supervisor notified:
(Print Name) D i b.. RETURN'this procedureg to Health Physics for release cancellaion.
3.Chemistry'DepartinnL I have reviewed Part C and have verified It is accurat Verification Date Time
- 14. ,PROMPTL..Y DELIVER this release package to Health Physics for processing (ENSURE receipt Is acknowledged).
11
BwOP WX-501T1 Revision 19 Continuous Use D. HE H PHSICS DEPARTM RPONSI ILI RADIONUCLIDE ANALYSIS If ORE-PR0OI (Liquid RadwasteNOTE two release tank samples must Release Monitor) is otit-of-service be obtained and analyzed. For all release calculations the amvm- oonceragond, (from the two analyses) SHALL be each isot.pe used. If an Isotope appears on only one of the two analyses, then use that value for the isotope.
Obtain the following and attach to this release form:
- a. isotoplc(s) fd. the tank to be released.
-- &2. CALL the Unit Supervisor and VERIFY that there are no *Liquid Release in.
PrOgress placards on panel OPMO1J. A,.DfP z C7r Steps D.3, D.4, and D.5 are notNOTE required if ORE-PR001 Is inoperable nd AAR OBwOS RETS 2.1-1a has been initiated.
- 3. Call the OPS Supervisor for the following:
, -re-
- a. Verify no OWX026T release package (BwOP WX-526T1) is in progress past Step D.2 and prior to Step 1.1.
- b. Verify that the backflush of the ORE-PR001 was completed more than IQ minutes ago.
- c. Verify that the OPROIJ return is lined up to 0WX01T by either
- 1) Checking Placard on Radwaste Control Panel OR
- 2) Performing the following valve lineup:
a) OPEN "No EPN", OPRO1J return to 0WX01T.
b) CLOSE "No EPNw, OPROIJ return to OWX26T.
12
BwOP WX-501Ti Revision 19 Continuous Use D, 4. Call the NSO and Request the 3 most recent IQ minute average readings from RM-11 for the ORE-PRO01 (OPSI01). 4 .- JZ*
Date:.- f" f Time: ,-.k 02 4, AX. r pCl/mW.;*
- 3 1lt- *C/i s ft -
"5. Re fthe maximumbackgr forW 'iained fom 3 average*
readings In Step D.4. above = Le f- Ci/rmd NOTE If a conputedzed release program is available, you may attach the printout to this form and irnicate "see attached" In the calculation aspace.in Step D.6.a: belW*'*I nboquantifiable peaks are found In the radlonudide analysis, writ "NQPF" in the Table In Step D.6.a.
Actual release data will e oompleted In Secto I.
AL 6. RADIOACTIVE RELEAAE RATE DETERMINATION:
- a. To ensure compliance of the planned release with 10CFR20 imits and BwRP 6110-12, COMPLETE the table below. If an Isotope is not present, you may leave the space blank.
13
BwOP WX-501T1 Revision 19 Continuous Use D. 6. a.
NOTE DWC values are listed in 10CFR20, Appendix B Table 2, Column 2.
For Tech Spec Unit take ten times the DWC value for each isotope listed for column 3. (i.e. the DWC value for Co-88 is 2E-5 pCI/mI.
The value listed in column 3 below would be 2E-4 pCI/m.) The Tech Spec Umit for noble gas isotopes is 2E-4 pCift4 per ODCM Radioactive Effluent Technical Standard 12.3.1 A.
- 1 Anly e TW,*y.Te h .A li mi Tank Adh#20 4ft fIuLKm ), (Thls Column #6 Not IsotopeyTc Tech Spec ULmit (pClWm) Completed until Step Qgi.
______ _ _F") Unrestricted Area DWC Fracdon Na-24 ____MM_.0,__ _____,________-3____,____.,
Cr-51
/ f * ..
- *,o-57 . "l /' . -4.
0!98*
E-4,_,
e,-_I_
-050
-92 f L_ . E-4.
95 .0 E-4..
W-97 _.0 E-5__
Sg-1lom _.0E-5_
rc-99m I_,_,_.1.0 E-2 n-i 13 3.0 E-4 fb-122 1.0 E-4 tb-124 _.0 E-5__
125 3.0 E-4 _ _
b-126 _.0 E-5___
s-136 _.0 E-5/ __.0___E-j__ __
1-131
-133 E_5 _.0 e-133 Z.0 E .* _.0_E__
9e-133m s-134 .0 E-6 -----
e-135 _.0 E-4__--_ _.,,._
s-137 _1.0 E-5 5-138 4.0 E-3 a-140 8.0 E-5 a-140 9.0 E-5 e-144 3.0 E-5_.. . .
-3 1.0 E-2 otal _ Total_ __ _ _.
(2) Sum of column #2 does NOT indude Tritium (4) Sum of column #4 DOES include Tritium 14
BwOP WX-501TI Revision 19 Continuous Use D.#6 b. VERIFY that the total tank curies excluding noble gas and tritium, are less than the administratve limit. If exceeded, receive permission from the OPS Supervisor to release the tank.
OPS, Supersor Contacted (print) or N/A Date. Time
'Circulati* n Water Blowdown. = L.OGPM.
-d 'RADIOACTIVE RELEASE RAWE SA.
CbadUafing Water Blo~wdo"~ Rate (8, 000 Spm)] 12 Radioactive Release Rate-
- 1. Total of Columnn4 j
- 4t- L GPM Date: .- :5A- Time: &1&
(niot t6 ,9XcwWed .gum)
IL e. MAXIMUM RELEASE RATE DETERMINATION:"
CHOOSE the riost Nnhftg (smallost) release ra.. saler the Chemos, release Me *dM 8te C.10 or the Radioactive Release Rate in I.,,-
Step D.6.d. above.
MAMUM RELEASE RATE GM/
P
- f. Calculate the rninmu release duration using formula below.
Minimum Release = ITank Volume (Gal) - 33001 = Z Min Duration Max. Release Rate (GPM)
AK g. UNRESTRICTED AREA DWC FRACTION (Verification):
- 1) COMPLETE column #5 of Step D.6.a. using the following equation on a radionudide basis:
DW'C Fraction [Analyzed Tank Activity ( pC&M) x Max. Release Rate (gpm) 1 .Teh Sp Limit Max. Release Rate (gpm)+ Circ Water Blowdown Rate (8,000 (gpm)J
- 2) VERIFY the sum of column #5 is less than 0.5. If not, NOTIFY the OPS Supervisor and CANCEL this release form.
15
BwOP WX-50IT1 Revision 19 Continuous Use NOTE Step D.7. Is not required if ORE-PR001 Is Inoperable and AAR OBwOS RETS 2.1-1ahas been initiated.
D&7. RADWASTE EFFLUENT MONIT' "T' a.: DETERAMNE the*Aet Alam anf High Alarm *ir 10.the ULi,.. ,
Radwwaste Effluent Monitor (ORE-PR001) using the following equation:
ORE-PRO01 maxdmum baIckrrounl from Step D.5.
Calcuaed ORE-PR001 setpolnt = [(Total Analyzed Tank aclMty*) x 1.5].
+ (Ma;. 0W.-PR001: 8kg).
io bf:cmn 2 Step D.6.a.
gi RECORD the cacltdOEP Isetpoknt fut liCilrvd 60OW~ARE Vi ecltdORE-P3ROft setpolnt to each oif the cuffrret ORE-PROOI nmnitor setpoints. These setpoints are:
1.31E-4 piCI/n! for the HIGH setpoint 6.56E-5 LCI/rkd for the ALERT setpoint If the calculated value Is less than the current monitor setlpont, RECORD the current monitor setpolnt as the Release setpolnt. If the calculated value is greater than the current monitor setpoint, RECORD the calculated value as the Release setpoint.
- b. RECORD ORE-PRO01 Monitor Liquid Release selpoints:
4L Chan Item 9 (HIGH Alarm Setpoint) 6IUi L jaCi/ml Chan Item 10 (ALERT Alarm Setpoint) S.1IC-4 jCi/rml 16
BwOP WX-501T1 Revision 19 Continuous Use NOTE Step D.8. is not required iNORE-PR010 is inoperable and AAR 0BwOS RETS 2.1-1a has been initiated.
- D. 8. STATION BLOWDOWN MONITOR SOPOINT-."
4 T~~~NE140 ALE.RT Alau qhHSI lcipl Rrm hIn
.. .Blo'wsee Monior ORE-PRO10 using'the follokwg equation:
ORE-PR0IO ORE-PR00* 1.25 x Total Analgzed Tank AclvItv x Max Rtelease Rate Selpolt ourent Circ. Water Blowdown Rat of LM gpm + Max Release Rate rea*U...
- Sum of column #2, Stop D.6.a.
.ORE-PROIO current veading.
- I--.
- S.
Celculp 0ftm3O-PRQ1O t~poWn _..c.oMUT I-COMPARE the calculated ORE-PR01 0 Setpolnt to each of w current monitor se#*pft. Thee setponts. are:
8.19E-6 pCv/ml for the HIGH setpoint 5.73E-6 pCimni for the ALERT setpoint Ifthe calculated value Is less than the current monitor selpoint, RECORD the current monitor setpolnt as the Release setpolnt. If the calculated value is greater than the current monitor setpoint, RECORD the calculated value as the Release setpoint.
- b. RECORD ORE-PR010 Monitor Liquid Release setpoints:
Chan Item 9 (HIGH Alarm Setpolnt) L2Ef,*! paCi/mi AL Chan Item 10 (ALERT Alarm Setpoint) 6.2f,.-& pCi/mI 17
BwOP WX-501T1 Revision 19 Continuous Use D. 9. APPROVAL FOR RADIOLOGICAL RELEASE:
Radiation Protection: I have review Part D and have verifed it is accurate and ornDteeTim *
"-- NOTE vI Is 7AA MO OBwOS RETS W for Step 2.1-1a has D.9.
beenIf ORE-PRoo Initiate. IsInoperable and RP or Chem* I have verified that Part D Is accurate and cornplete.
VERIFICATION Date: Time:________
fOr Ins jcti6s 0to owAMt this package.
18
BwOP WX-501T1 Revision 19 Continuous Use E. OPERATING DEPARTMENT RESPONSIBILITY NOTE A Check Source Check is a verification of Detector Response. Even if Detector response is immediately evident when a "Hor Release
'Tank is first lined up to OPRO1J, ODCM RETS 2.1.1B-1 requires a
'Source Check. If a Check Source Test fails When High Activity is present, it is caused by the program function of OPROIJ. To pass the Check Source Test, the Activity has to-stabiliZe or be nissed, and repeated attempts may have to be performed until successful.
NOTE Step E.1. is not required if ORE-PR001 is inoperable and AAR OBwOS RETS 2.1-1a has been initiated.
- 1. Perform OBwOS RETS 2.1.B-1, "Unit Common Pre-Release Source Check of Liquid Effluent Monitor OPROIJ."
Time: Date:
- 2. Control Room Supervisor: I have verified that either the OBwOS RETS 2.1.13-1 Acceptance Criteria has been met, or ORE-PR001 is inoperable.
reLJ aEjA&I Room Sufmrvisor m J/1ý Date NOTE Generally, a low flow release rate should be considered as <130 gpm. Contact OPS Supervisor for determination of which release flow path to use based on current conditions, equipment availability, etc.
- 3. CONTACT OPS Supervisor for release flow rate path.
- 4. CIRCLE release flow rate path. Low FlowfHigh Flow.
19
BwOP WX-501T1 Revision 19 Continuous Use NOTE Step E.5. is not required if ORE-PR010 is inoperable and AAR OBwOS RETS 2.1-1a has been initiated.
E. 5. OBTAIN and RECORD the values of the following CHAN ITEMS for the ORE-PR010 (OPSI 10) from its CHAN ITEM Display on the RM-1 1 Console.
(DEPRESS Grid I key, key in 110, DEPRESS SEL key and then DEPRESS CHAN ITEMS key).
- a. Chan Item 9 (HIGH Alarm Setpoint) _iCi/mI
- b. Chan Item 10 (ALERT Alarm Setpoint) _jCi/mI NOTE Step E.6. is not required if ORE-PRO01 is inoperable and AAR OBwOS RETS 2.1-1a has been initiated.
- 6. OBTAIN and RECORD the values of the following CHAN ITEMS for the ORE-PRO01 (OPS101) from its CHAN ITEM display on the RM-1 1 Console.
(DEPRESS GRID 1 key, key in 101, DEPRESS SEL key and then DEPRESS CHAN ITEMS key).
- a. Chan Item 9 (HIGH Alarm Setpoint) _iCi/ml
- b. Chan Item 10 (ALERT Alarm Setpoint) _ pCi/ml 20
BwOP WX-501T1 Revision 19 Continuous Use E. 7. VERIFY OBwOSR 0.1-0 daily channel check is complete on:
NOTE Step E.7.a. is not required if ORE-PR001 is inoperable and AAR OBwOS RETS 2.1-1a has been initiated.
- a. -Rad Monitor0ORE-PRO01: Liquid Radwaste Effluent.
NOTE Step E.7.b. is not required if ORE-PR0lO is inoperable and AAR OBwOS RETS 2.1-l a has been initiated.
- b. Rad Monitor ORE-PR010: Station Blowdown.
NOTE Step E.7.c. is not required if OUR-CW032 is inoperable and AAR OBwOS RETS 2.1-1a has been initiated.
- c. Station Blowdown Line Monitor Loop OUR-CW032.
21
BwOP WX-501T1 Revision 19 Continuous Use NOTE Steps E.8. and E.9. are not required if ORE-PR001 is inoperable and AR 0BwOS RETS 2 .1-1a has been initiated.
NOTE Foe a release through the low flow rate path and mark step E.9 N/A. If a high flow COMPLETE Step E.8 rate release, PROCEED to Step E.9 and mark step E.8 N/A.
NOTE If the OPRO1J is in High Alarm at this point in the procedure due to high background, it will be necessary to reset the HIGH alarm setpoint to a value higher than the background.
OAOV-WX896 to open to test the interlock This will allow the function. Otherwise, Step E.8.f. is not required.
NOTE Upon receipt of a high radiation signal at 0PR01J, Discharge Valves, 0WX353 and 0WX896 the Release Tank will remain closed until the high radiation signal seal-in is reset at OPLOIJ.
E. 8. VERIFY valve OAOV-WX896, Release Tank Disch Isolation Valve, automatically closes on high radiation by PERFORMING the following Steps:
- a. VERIFY sufficient blowdown flow is established.
- b. VERIFY/CLOSE OAOV-WX897, Flow Control Radwaste Effluent Discharge Valve.
- c. VERIFY/CLOSE OAOV-WX890, Release Tk Pp OWX53P Dsch Isol.
- d. VERIFY/OPEN OAOV-WX889, Release Tk Pp OWX01 P Dsch Isol.
- e. VERIFY/START 0WX01 P, Release Tank Pump.
22
BwOP WX-501T1 Revision 19 Continuous Use E 8 f. IF the OPRO1J is in HIGH alarm, CHANGE the HIGH alarm setpoint value higher than background. to a This will allow the RELEASE TANK DISCHARGE HEADER RADIATION OPLO1J) to be reset, and the OAOV-WX896 HIGH alarm (Window 77A09 on seal-in has been reset. This can valve to be opened after its be accomplished as follows:
W CAUTION Some actions possible in the Supervisor serious detrimental effects Mode may have W on system operation.
Therefore use caution when in this mode and do not leave the RM-1 1 console unattended when it is in this mode.
- 1) PLACE the RM-1 1 Console in SUPERVISOR MODE.
- 2) SELECT the HIGH alarm setpoint (channel item 9) to be changed on the ORE-PR001 (OPS101) CHAN ITEMS display by KEYING in 9 and DEPRESSING the SEL key.
(Following this CHAN ITEM 9 should be displayed in reverse characters.)
- 3) ENTER a HIGH alarm setpoint USING value of 3.76E-10 would be entered The format XYZ +/- AB (i.e. a as 376-10) and DEPRESS the ENTER key. The new value will be displayed after a short delay.
- g. VERIFY/CLEAR RELEASE TANK DISCHARGE HEADER RADIATION HIGH Annunciator (Window 77A09 on OPLO1J).
Upon receipt of a high radiationNOTE signal at OPROIJ, the Release Tank Discharge Valves, 0WX353 and 0WX896 will remain closed until high radiation signal seal-in is reset the at OPLO1J.
- h. OPEN 0AOV-WX896, Release Tank Disch Isolation Valve.
23
BwOP WX-501T1 Revision 19 Continuous Use E. 8. i. AUTO CLOSE valve OAOV-WX896, Release Tank Disch Isolation Valve, by LOWERING the Liquid Radwaste Effluent monitor ORE-PR001 HIGH alarm setpoint to a value below the current activity as follows:
- 1) PLACE the RM-11 Console in SUPERVISOR MODE.
- 2) SELECT the HIGH alarm setpoint (channel item 9) to be changed on the ORE-PR001 (OPS101) CHAN ITEMS display by KEYING in 9 and DEPRESSING the SEL key.
(Following this CHANITEM 9 should be displayed in reverse characters.)
- 3) RECORD the current activity reading.
- 4) ENTER a new HIGH alarm setpoint below the current activity value (from the upper right corner of the display) USING the format XYZ +/- AB for XYZ E +/- AB (i.e. a value of 3.76E-10 would be entered as 376-10).
- 5) RECORD the new HIGH alarm setpoint that was entered.
(channel item 9) _
- 6) DEPRESS the ENTER key.
- 7) ACKNOWLEDGE the alarm at the RM-1 1 console.
- j. VERIFY OAOV-WX896, Release Tank Disch Isolation Valve, Auto Closes.
- k. VERIFY RELEASE TANK DISCHARGE HEADER RADIATION HIGH alarm (Window 77A09 at OPLO1J) annunciates at OPL01J and ACKNOWLEDGE.
PLACE key locked switch for OAOV-WX896, Release Tank Disch Isolation Valve, in CLOSE.
24
BwOP WX-501T1 Revision 19 Continuous Use Some actions possible in the Supervisor serious detrimental effects on system Mode may have operation.
Therefore use caution when in this mode and do not leave the RM-1 1 console unattended when it is in this mode.
E 8. m. VERIFY/ADJUST the ALERT Alarm and HIGH Alarm setpoints for ORE-PR001 (OPS101) to the values specified by Health Physics in Step D.7.b. USING the instructions that follow.
VERIFICATION
- 1) PLACE the RM-1 1 Console in SUPERVISOR MODE.
- 2) SELECT the ALERT alarm setpoint (channel item 10) to be changed on the ORE-PRO01 (OPS101) CHAN KEYING in 10 and DEPRESSING the SEL ITEMS display by key.
CHAN ITEM 10 should be displayed in reverse (Following this characters.)
- 3) ENTER the new ALERT alarm setpoint USING the format XYZ +
AB (i.e. a value of 3.76E-10 would be entered DEPRESS the ENTER key. The new value as 376-10) and will be displayed after a short delay.
- 4) SELECT the HIGH alarm setpoint (channel item 9) to be changed on the ORE-PR001 (OPS101) CHAN ITEMS 9 and DEPRESSING the SEL key. (Following display by KEYING in this CHAN ITEM 9 should be displayed in reverse characters.)
- 5) ENTER the new HIGH alarm setpoint USING the format XYZ +/- AB (i.e. a value of 3.76E-10 would be entered DEPRESS the ENTER key. The new value as 376-10) and will be displayed after a short delay.
- n. VERIFY/CLEAR RELEASE TANK DISCHARGE HEADER RADIATION HIGH annunciator (Window 77A09 at OPL01J).
25
BwOP WX-501T1 Revision 19 Continuous Use NOTE If the 0PR01 J is in High Alarm at this point in the procedure due to high background, it will be necessary to reset the HIGH alarm setpoint to a value higher than the background. This will allow the OAOV-WX353 to open to test the interlock function. Otherwise, Step E.9.f. is not required.
E. 9. VERIFY valve 0WX353, Release Tank Disch Isolation Valve, automatically closes on high radiation by PERFORMING the following Steps for a release through the high flow rate path:
- a. VERIFY sufficient blowdown flow is established.
- b. CLOSE OAOV-WX302, Flow Control Radwaste Effluent Discharge Valve.
- c. VERIFY/CLOSE OAOV-WX890, Release Tk Pp OWX53P Dsch Isol.
- d. VERIFY/OPEN OAOV-WX889, Release Tk Pp OWX01P Dsch Isol.
- e. VERIFY/START 0WX01 P, Release Tank Pump.
26
BwOP WX-501T1 Revision 19 Continuous Use CAUTION Some actions possible in the Supervisor Mode may have V serious detrimental effects on system operation. "
Therefore use caution when in this mode and do not leave the RM-11 console unattended when it is in this mode.
E 9. f. IF the OPR01J is in HIGH alarm, CHANGE the HIGH alarm setpoint to a value higher than background. This will allow the RELEASE TANK DISCHARGE HEADER RADIATION HIGH alarm (Window 77A09 on OPLO1J) to be reset, and the OAOV-WX353 valve to be opened after its seal-in has been reset. This can be accomplished as follows (N/A if OPROIJ is not in alarm):
- 1) PLACE the RM-1 1 Console in Supervisor Mode.
- 2) SELECT the HIGH alarm setpoint (channel item 9) to be changed on the ORE-PRO01 (OPS101) CHAN ITEMS display by KEYING in 9 and DEPRESSING the SEL key. (Following this CHAN ITEM 9 should be displayed in reverse characters.)
- 3) ENTER a HIGH alarm setpoint USING the format XYZ + AB (i.e. a value of 3.76E-10 would be entered as 376-10) and DEPRESS the ENTER key. The new value will be displayed after a short delay.
- g. VERIFY/CLEAR RELEASE TANK DISCHARGE HEADER RADIATION HIGH Annunciator (Window 77A09 on OPL01J).
NOTE Upon receipt of high radiation signal at 0PR01J, the Release Tank Discharge Valves, 0WX353 and 0WX896 will remain closed until the high radiation signal seal-in is reset at OPL01J.
- h. OPEN OAOV-WX353, Release Tank Disch Isolation Valve. (The key to operate the OAOV-WX353 valve control switch must be obtained from the OPS Supervisor or Shift Manager.)
27
BwOP WX-501T1 Revision 19 Continuous Use E. 9. i. AUTO CLOSE valve OAOV-WX353, Release Tank Disch Isolation Valve, by LOWERING the Liquid Radwaste Effluent monitor ORE-PR001 HIGH alarm setpoint to a value below the current activity as follows:
- 1) PLACE the RM-1 1 Console in SUPERVISOR MODE.
- 2) SELECT the HIGH alarm setpoint (channel item 9) to be changed on the ORE-PR001 (OPS101) CHAN ITEMS display byKEYING in
.9 aS..
n d D E P R E S S IN G th e S E L ke y - ( F o llow in g this C HAN ITE M 9 should be displayed in reverse characters.)
- 3) RECORD the current activity reading
- 4) ENTER a new HIGH alarm setpoint below the current activity value (from the upper right corner of the display)
USING the format XYZ +/- AB for XYZ E +/- AB (i.e. a value of 3.76E-10 would be entered as 376-10).
- 5) RECORD the new HIGH alarm setpoint that was entered.
(channel item 9)
- 6) DEPRESS the ENTER key.
- 7) ACKNOWLEDGE the alarm at the RM-1 1 console.
- j. VERIFY OAOV-WX353, Release Tank Disch Isolation Valve, Auto Closes.
- k. VERIFY RELEASE TANK DISCHARGE HEADER RADIATION HIGH alarm annunciates at OPL01J and ACKNOWLEDGE.
PLACE key locked switch for OAOV-WX353, Release Tank Disch Isolation Valve, in CLOSE.
28
BwOP WX-501T1 Revision 19 Continuous Use CAUTION Some actions possible in the Supervisor serious detrimental effects Mode may have on system operation.
V Therefore use caution when in this mode and do not leqve the RM-1 1 console unattended mode. when it is in this E 9. m. VERIFY/ADJUST the ALERT Alarm and HIGH Alarm setpoints for ORE-PR001 (OPS101) to the values specified by Health Physics in Step D.7.b. USING the instructions that follow.
VERIFICATION
- 1) PLACE the RM-1 1 Console in SUPERVISOR MODE.
- 2) SELECT the ALERT alarm setpoint (channel item 10) to be changed on the ORE-PR001 (OPS101)
KEYING in 10 and DEPRESSING CHAN ITEMS display by the SEL key. (Following this CHAN ITEM 10 should be displayed in reverse characters.)
- 3) ENTER the new ALERT alarm setpoint USING the format XYZ +/-
AB (i.e. a value of 3.76E-10 would DEPRESS the ENTER key. The be entered as 376-10) and new value will be displayed after short delay. a
- 4) SELECT the HIGH alarm setpoint (channel item 9) to be changed on the ORE-PR001 CHAN ITEMS display by KEYING in 9 and DEPRESSING the SEL key. (Following this CHAN ITEM 9 should be displayed in reverse characters.)
- 5) ENTER the new HIGH alarm setpoint USING the format XYZ +/- AB (i.e. a value of 3.76E-10 would be entered as 376-10) and DEPRESS the ENTER key. The new value will be displayed after short delay. a
- n. VERIFY/CLEAR RELEASE TANK DISCHARGE HEADER RADIATION HIGH annunciator (Window 77A09 at OPL01J).
29
BwOP WX-501T1 Revision 19 Continuous Use NOTE Step E.10. is not required if ORE-PR010 OBwOS RETS 2.1-1a has been initiated is inoperable and AAR or if ALERT ALARM & HIGH ALARM setpoints have not changed from Step D.8.b.
E 10. VERIFY/ADJUST the ALERT and HIGH setpoints for ORE-PR010 to the values specified by Health Physics in Step D.8.b. using the instructions that follow.
VERIFICATION
- a. PLACE the RM-1 1 Console in Supervisor Mode.
- b. SELECT the ALERT alarm setpoint (channel item 10) to be changed on the ORE-PRO10 (OPS1 10) CHAN ITEMS display by KEYING in 10 and DEPRESSING the SEL key. (Following this CHAN ITEM 10 should be displayed in reverse characters.)
- c. ENTER the new ALERT alarm setpoint USING the format XYZ +/- AB (i.e. a value of 3.76E-10 would be entered as 376-10) and DEPRESS the ENTER key. The new value will be displayed after a short delay.
- d. SELECT the HIGH alarm setpoint (channel item 9) to be changed on the ORE-PR010 (OPS1 10) CHAN ITEMS display by KEYING in 9 and DEPRESSING the SEL key. (Following this CHAN ITEM 9 should be displayed in reverse characters.)
- e. ENTER the new HIGH alarm setpoint USING the format XYZ +/- AB (i.e. a value of 3.76E-10 would be entered as 376-10) and DEPRESS the ENTER key. The new value will be displayed after a short delay.
- f. PLACE the RM-1 1 Console in the NORMAL MODE.
30
BwOP WX-501T1 Revision 19 Continuous Use E. 11. RECORD the following data in the space provided.
- a. Circulating Water Blowdown Rate _ gpm (OUR-CW032 at PNL OPM01J, or computer Point F2400)
- b. VERIFY CW BLOWDOWN RATE IS EQUAL TO OR GREATER THAN 8.000 gpm.
- 12. Control Room Supervisor: I have reviewed Part E and have verified it is accurate and complete.
C /
Control Room Supervisor Date Time 31
BwOP WX-501T1 Revision 19 Continuous Use F. Shift Manager OR SRO RESPONSIBILITY
- 1. VERIFY that Steps B.6., C.13., D.9. and E.12. are signed.
NOTE Biocide treatment of CW requires isolation of CW blowdown. The expected time of release and release duration must be considered so that both biocide treatment and the release.can be accommodated.
- 2. VERIFY that the actual Circulating Water Blowdown Rate is equal to or greater than 8,000 gpm (OUR-CW032 at PNL OPM01J, or computer point F2400).
/
Shift Manager or SRO Date
- 3. PLACE a placard stating "Liquid Release in Progress" at OPM01J.
- 4. APPROVAL FOR RELEASE I Shift Manager or SRO Date Time
- 5. COMMENTS 32
BwOP WX-501T1 Revision 19 Continuous Use G. OPERATING DEPARTMENT RESPONSIBILITY - Discharging Release Tank 0WX01T to Circulating Water Blowdown Line.
NOTE If during the release, Circ Water Blowdown flow (Computer point F2400) is reduced to <§.00 gpm, terminate the release. Ifduring the release, Circ Water Blowdown flow is reduced to <7.000 gpm (low flow interlock setpoint), VERIFY the release is terminated. If Circ Water Blowdown flow can be re-established Ž8.000 gpm, the release may be restarted at step G.2 provided that the following conditions are met:
- Shift Manager permission is obtained.
- All applicable Steps are re-initialed/re-verified as necessary.
- No additions have been made to the Release Tank.
- Release totalizers have not been reset and the original totalizer readings are used to calculate the gallons released.
NOTE If Station Blowdown Line Flow Monitor (CW-032) is inoperable, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.
NOTE If this procedure is aborted before any effluent is released, perform Step G.27.a. through Step G.27.n. and realign the OPROIJ as directed by the OPS Supervisor, then perform Step G.28. and Step H. before exiting this procedure.
NOTE The purpose of the release window is to minimize the interaction with the City of Wilmington Water Department intake periods.
OPS Supervisor performs the following:
- a. RECORD the START AFTER time from step B.2. and the START BEFORE time from BwOP WX-501T2, RELEASE TIME TABLE, using the River Flow Rate from step B.1. and the release duration from step D.6.f.:
Start After Start Before 33
BwOP WX-501T1 Revision 19 Continuous Use G. 1. b. VERIFY release will start within release start time window recorded in step G. .a. If release cannot start within times recorded in step G.l.a. this step is N/A. Proceed to step G.1.c.
/ /
OPS Supervisor Date Time
- c. To start release outside of release start time window recorded in
'step G. l.a. VERIFY Authorization to Release Outside of Release Window, BwOP WX-501T3, is completed and retained'with this package.
OPS Supervisor Date Time NOTE If this procedure must be exited prior to its completion, the following temporary alteration must be restored per Step G.26. prior to exit.
- 2. PERFORM the following if AAR OBwOS RETS 2.1-1a is in effect for ORE-PR001 (refer to Step B.5.):
- a. OBTAIN Shift Manager or designee permission to perform the following Temporary Electrical Alteration.
SM/DESIGNEE VERIFICATION SUPERVISOR VERIFICATION
- b. REMOVE Relay Block K1 at OPR01J (inside the AC Power Panel) to allow opening of 0WX896/353, Release Tank Disch Isolation Valve.
SUPERVISOR VERIFICATION
- c. LOCALLY, at OPRO1J, place 2 placards stating "K1 RELAY REMOVED FOR LIQUID RELEASE":
- ONE on the AC Power Panel for OPR01J and,
- ONE on the Rad Detector Cabinet for OPRO1J.
34
BwOP WX-501T1 Revision 19 Continuous Use G. 3. RECORD the following data in the space provided.
- a. Tank Level Start %
(0LR-WX01I at PNL OPLO1J)
- b. VERIFY level in Step G.3.a. is +/-5% OF LEVEL RECORDED IN Step A.2 (Page 1), or receive Supervisor approval to continue.
- c. RESET the Batch Totalizer reading to zero at PNL OPLOIJ for the flowpath being used. (This step may be marked N/A if Batch Totalizer is inoperable.)
- d. RESET the Cumulative Totalizer reading to zero at PNL OPLO1J for the flowpath being used. (This step may be marked N/A if Cumulative Totalizer is inoperable.)
CAUTION Failure to record and use the correct maximum permissible release rate may result in violation of NPDES and/or IOCFR20 release criteria.
- e. Maximum Release Rate from Step D.6.e. (page 15) GPM SUPERVISOR VERIFICATION
- 4. STOP OWX36M, Release Tank Mixer (if applicable)
NOTE Step G.5. is not applicable if Steps E.I. and E.2. were not required.
- 5. VERIFY Steps E.I. and E.2. (page 19) have been completed within the previous 24 hrs (If NOT, RE-PERFORM Steps E.I. and E.2.).
NOTE Verification is required in Steps G.6. through G.13. if ORE-PROO is inoperable and AAR OBwOS RETS 2.1-1a has been initiated.
- 6. VERIFY/CLOSE OAOV-WX834, Release Tank Inlet Isolation Valve for Release Tank OWX01T.
SUPERVISOR VERIFICATION 35
BwOP WX-501T1 Revision 19 Continuous Use G 7. VERIFY/CLOSE OAOV-WX01 7, Release Tank Recycle Valve (Release Tank Discharge to Turbine Building Equipment Drain Tank Isolation Valve).
SUPERVISOR VERIFICATION
- 8. VERIFY/CLOSE OAOV-WX910, Release Tank Pump Disch Valve (Release Tank Discharge to Regeneration Waste Drain Tank).:
SUPERVISOR VERIFICATION . "__
- 9. VERIFY/CLOSE OAOV-WX302, Release Tank Discharge Control Valve/(High Flow Path).
SUPERVISOR VERIFICATION
- 10. VERIFY/CLOSE, OAOV-WX897, Release Tank Discharge Flow Control valve/(Low Flow Path).
SUPERVISOR VERIFICATION
- 11. VERIFY/OPEN OAOV-WX889, Release Tank Pump 0WX01 P Discharge Isolation Valve.
SUPERVISOR VERIFICATION NOTE For releases through the low flow rate path, < 130 GPM or as specified by OPS Supervisor, COMPLETE Step G.12 and mark step G.13 "N/A". For releases through the high flow rate path, mark Step G.12 "N/A" and PROCEED to Step G.13.
- 12. Low Flow Release, PERFORM the following:
- a. VERIFY Step E.8. (beginning on page 22) has been completed. (N/A if ORE-PR001 is inoperable and AAR OBwOS RETS 2.1-1a has been initiated)
- b. OBTAIN the key for OAOV-WX896, Release Tank Outlet Valve.
36
BwOP WX-501T1 Revision 19 Continuous Use NOTE If Circ. Water Blowdown Flow Low and/or Release Tank Disch Header Radiation High alarms are lit, it may be necessary to reset the Rel. Tank Disch Header & Isolation Valves 0WX896 & 0WX353 by pressing their reset button prior to opening 0AOV-WX896.
NOTE Upon receipt of a high radiation signal at OPROIJ, the Release Tank Discharge Valves, 0WX353 and 0WX896 will remain closed until the high radiation signal seal-in is reset OPLO1J.
G 12. c. OPEN OAOV-WX896, Release Tank Outlet Isolation Valve.
SUPERVISOR VERIFICATION
- d. VERIFY/CLOSE OAOV-WX015, Release Tank 0WXO1T Pump Recirc Valve.
SUPERVISOR VERIFICATION
- e. SLOWLY OPEN OAOV-WX897, Release Tank Discharge Flow Control Valve,(Low Flow Path) with controller OFK-WX630, TO OBTAIN a maximum discharge flowrate of 50 GPM, or less than 50 GPM if required by Step D.6.e., for the first three (3) minutes of the release by checking at least one of the following:
O Low Flow Totalizer increasing.
O Low Flow Recorder increasing.
o OWX01T Level Recorder decreasing.
O Computer Point (F0002) for release rate increasing.
SUPERVISOR VERIFICATION
- f. RECORD Release Start Time Date:
SUPERVISOR VERIFICATION 37
BwOP WX-501T1 Revision 19 Continuous Use G 12. g. SLOWLY OPEN OAOV-WX897, Release Tank Discharge Flow Control Valve, with controller OFK-WX630, To OBTAIN a release rate NOT to exceed the maximum release rate specified in Step G.3.e.
SUPERVISOR VERIFICATION
- 13. High Flow Release, PERFORM the following:
.a. VERIFY Step E.9. (beginning on page 26) has been completed. (N/A if ORE-PR001 is inoperable and AAR OBwOS RETS 2.1-1a has been initiated.)
- b. OBTAIN the key for 0AOV-WX353, Release Tank Outlet Valve.
NOTE If Circ. Water Blowdown Flow Low and/or Release Tank Disch Header Radiation High alarms are lit, it may be necessary to reset the Rel. Tank Disch Header & Isolation Valves 0WX896 & 0WX353 by pressing their reset button prior to opening 0AOV-WX353.
NOTE Upon receipt of a high radiation signal at OPR01J, the Release Tank Discharge Valves, 0WX353 and 0WX896 will remain closed until the high radiation signal seal-in is reset OPL01J.
- c. OPEN OAOV-WX353, Release Tank Outlet Isolation Valve.
SUPERVISOR VERIFICATION
- d. VERIFY/CLOSE OAOV-WX015, Release Tank 0WX01T Pump Recirc.
Valve.
SUPERVISOR VERIFICATION 38
BwOP WX-501T1 Revision 19 Continuous Use G 13. e. SLOWLY OPEN OAOV-WX302, Release Tank Discharge Flow Control Valve, with controller 0FK-WX001, TO OBTAIN a maximum discharge flowrate of 50 GPM for the first three (3) minutes of the release by checking at least one of the following:
o High Flow Totalizer increasing.
o High Flow Recorder increasing.
o 0WX01T Level Recorder decreasing.
p O Computer Point (F0001) for release rate increasing.
SUPERVISOR VERIFICATION
- f. RECORD Release Start Time
- Date:
SUPERVISOR VERIFICATION
- g. SLOWLY OPEN OAOV-WX302, Release Valve, with controller OFK-WX001, TO Tank Discharge Flow Control OBTAIN a release rate not to exceed the maximum release rate specified in step G.3.e.
SUPERVISOR VERIFICATION
- 14. RECORD the Release Rate -GaVMin SUPERVISOR VERIFICATION (LESS THAN MAXIMUM RATE DETERMINED IN STEP G.3.e.)
- 15. VERIFY the following:
NOTE Step G.15.a. is not required if Batch and Cumulative Totalizers are not operable. Gallons released shall be determined per note prior to Step G.20.e. if both totalizers are not operable.
- a. Batch Totalizer and/or Cumulative Totalizer readings increase. (It acceptable, however, to observe no is increase in the readings at low release rates).
39
BwOP WX-501T1 Revision 19 Continuous Use NOTE Step G. 15.b. is not required if OFR-WX630-1 applicable, is inoperable and AAR OBwOS or OFR-WX630-2, as identified. RETS 2.1. 1a has been G 15. b. PERFORM a Channel Check per OBwOSR 0.1-0 OFR-WX630-2, as applicable, by OBSERVING for OFR-WX630-1 or indication at OPL01J.
NOTE Step G. 15.c. is not required if OUR-CW032 is inoperable and AAR 0BwOS RETS 2.1-1a has been identified.
- c. PERFORM a channel check per OBwOSR Flow Monitor by observing OUR-CW032, 0.1-0 for the Station Blowdown indicated on Panel OPMO1J, or computer point F2400.
- d. RECORD Station Blowdown Flowrate during release: _ gpm
- e. RECORD Station Blowdown Flowrate once per 24 Hr. on continuous release: gpm (N/A if not applicable)
- f. NOTIFY Control Room of release in progress.
- g. NOTIFY Shift Manager of release in progress.
40
BwOP WX-501 T1 Revision 19 Continuous Use G. 16. PERFORM the following rate checks. REFER to Attachment A as needed.
- a. For the high flow rate path check the flow rate using a tank level calculation over a 10 minute interval against computer point F0001 or Flow Recorder. PERFORM this check twice at release and again when < 50% level. RECORDthe beginning of the each flow rate obtained.
b., For the low flow rate release path check the flow rate calculation over a 10 minute interval against using a tank level Flow Recorder. PERFORM this check computer point F0002 or twice at the beginning of the release. Providing the flow rates are consistent and below the allowed release rate the release flow rate checks can be relaxed to once every 30 minutes. RECORD each flow rate obtained.
Where: At = Stop Time - Start TIME Al = Stop LEVEL - Start Level 29 = gallons per 1% tank level After each check of flowrate, VERIFY the flowrate is less rate specified in step D.6.e. and/or G.3.e, than the maximum release if not, IMMEDIATELY NOTIFY the OPS Supervisor.
41
BwOP WX-501T1 Revision 19 Continuous Use Attachment A Liquid Release Rate Chart
%Level I % Time Change Change 5.00 1 10.00 15.00 20.00 25.00 30.00 35.00 1 40.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.50 32.90 16.45 10.97 8.23 6.58 5.48 4.70 4.11 1.00 65.80 32.90 21.9. 16.45 13.16 10.97 9.40 8.23 1.50 98.70 49.35 32.90 24.68 19.74 16.45 14.10 12.34 2.00 131.60 65.80 43.87 32.90 26.32 21.93 18.80 16.45 2.50 164.60,. 82-25 54.83 41.13 32.90 27.42 23.50 20.56 3.00 197.40 98.70 .65.80 49.35 .39.48 32.-0 28.20 24.68 3.50 230.30 115.15 76.77 57.58 46.06 38.38 32.90 28.79 4.00 263.20 131.60 87.73 65.80 52.64 43.87 37.60 32.90 4.50 296.10 148.05 98.70 74.03 59.22 49.35 42.30 37.01 5.00 329.00 164.50 109.67 82.25 65.80 54.83 47.00 41.13 5.50 361 90 180.95 120.63 90.48 72.38 60.32 51.70 45.24 6.00 394.80 197.40 131.60 98.70 78.96 65.80 56.40 49.35 6.50 427.70 213.85 142.57 106.93 85.54 71.28 61.10 53.46 7.00 460.60 230.30 153.53 115.15 92.12 76.77 65.80 57.58 7.50 493.50 246.75 164.50 123.38 98.70 82.25 70.50 61.69 8.00 526.40 263.20 175.47 131.60 105.28 87.73 75.20 65.80 8.50 559.30 279.65 186.43 139.83 111.86 93.22 79.90 69.91 9.00 592.20 296.10 197.40 148.05 118.44 98.70 84.60 74.03 9.50 625.10 312.55 208.37 156.28 125.02 104.18 89.30 78.14 10.00 658.00 329.00 219.33 164.50 131.60 109.67 94.00 82.25 10.50 690.90 345.45 230.30 172.73 138.18 115.15 98.70 86.36 11.00 723.80 361.90 241.27 180.95 144.76 120.63 103.40 90.48 11.50 756.70 378.35 252.23 189.18 151.34 126.12 108.10 94.59 12.00 789.60 394.80 263.20 197.40 157.92 131.60 112.80 98.70 12.50 822.50 411.25 274.17 205.63 164.50 137.08 117.50 102.81 13.00 855.40 427.70 285.13 213.85 171.08 142.57 122.20 106.93 13.50 888.30 444.15 296.10 222.08 177.66 148.05 126.90 111.04 14.00 921.20 460.60 307.07 230.30 184.24 153.53 131.60 115.15 14.50 954.10 477.05 318.03 238.53 190.82 159.02 136.30 119.26 15.00 987.00 493.50 329.00 246.75 197.40 164.50 141.00 123.38 15.50 1019.90 509.95 339.97 254.98 203.98 169.98 145.70 127.49 16.00 1052.80 526.40 350.93 263.20 210.56 175.47 150.40 131.60 16.50 1085.70 542.85 361.90 271.43 217.14 180.95 155.10 135.71 17.00 1118.60 559.30 372.87 279.65 223.72 186.43 159.80 139.83 17.50 1151.50 575.75 383.83 287.88 230.30 191.92 164.50 143.94 18.00 1184.40 592.20 394.80 296.10 236.88 197.40 169.20 148.05 18.50 1217.30 608.65 405.77 304.33 243.46 202.88 173.90 152.16 19.00 1250.20 625.10 416.73 312.55 250.04 208.37 178.60 156.28 19.50 1283.10 641.55 427.70 320.78 256.62 213.85 183.30 160.39 20.00 1316.00 658.00 438.67 329.00 263.20 219.33 188.00 164.50 20.50 1348.90 674.45 449.63 337.23 269.78 224.82 192.70 168.61 21.00 1381.80 690.90 460.60 345.45 276.36 230.30 197.40 172.73 21.50 1414.70 707.35 471.57 353.68 282.94 235.78 202.10 176.84 22.00 1447.60 723.80 482.53 361.90 289.52 241.27 206.80 180.95 22.50 1480.50 740.25 493.50 370.13 296.10 246.75 211.50 185.06 23.00 1513.40 756.70 504.47 378.35 302.68 252.23 216.20 189.18 24.00 1579.20 789.60 526.40 394.80 315.84 263.20 225.60 197.40 24.50 1612.10 806.05 537.37 403.03 322.42 268-68 230.30 201.51 25.00 1645.00 822.50 548.33 411.25 329.00 274.17 235.00 205.63 Enter % Enter Flow Rate Change - Time -
42
BwOP WX-501T1 Revision 19 Continuous Use NOTE Closing the OAOV-WX889 will isolate sample ORE-PR001, thus causing it to interlock, flow to the and subsequently close the applicable flow path's Release Tank Discharge Isolation Valve (OAOV-WX353 or OAOV-WX896).
G. 17. IF the release MUST be interrupted to provide the operator a break when a relief is unavailable, THEN perform the following:
- a. Receive permission from the Shift Manager to secure the release for no more than 30 minutes.
- b. Make a log entry and an entry on the table in step G.16. denoting the time the release was stopped.
- c. OPEN OAOV-WX01 5, Release Tank Pump 0WX01 P Recirc Valve.
NOTE Notify Main Control Room prior to closing OAOV-WX889 as this action will generate an RM-1 1 alarm.
- d. CLOSE OAOV-WX889, Release Tank Pump OWX01P Discharge Isol Valve.
- e. VERIFY that the release has been stopped.
- f. MINIMIZE the pause in the release.
- g. NOTIFY Shift Manager that release will be started again.
- h. Make a log entry and an entry on the table in Step G.16. denoting the time which the release was restarted.
- i. OPEN 0AOV-WX889, Release Tank Pump 0WX01T Discharge Isol Valve.
- j. VERIFY Release Tank Discharge Header Radiation High alarm at OPL01J CLEARS.
43
BwOP WX-501T1 Revision 19 Continuous Use Upon receipt of a high radiationNOTE signal at OPRO1J, the Release Tank Discharge Valves, 0WX353 and 0WX896 will remain closed until the high radiation signal seal-in is reset at OPLO1J.
G. _17. k. VERIFY/OPEN 0AOV-WX353/896, Release Tank Discharge Isolation Valve, for the flow path being used.
I. CLOSE 0AOV-WX015, Release Tank OWX01T Pump Recirc Valve.
Tripping the release tank pumpNOTE will stop sample flow to the ORE PR001 ,thus causing it to interlock. The main notified prior as this will generate an RM-11 control room should be alarm.
- 18. WHEN the desired volume of water has been released from Release Tank OWX01T, TRIP Release Tank Pump 0WX01P.
Verification is required for step NOTE G.19. if ORE-PRO01 is inoperable and MAR OBwOS RETS 2 .1-1a has been initiated.
- 19. CLOSE OAOV-WX302/897, Release Tank Discharge Flow Control Valve.
SUPERVISOR VERIFICATION
- 20. RECORD the following:
- a. Release Stop Time:
Date:
- b. Tank Level Final
- c. Batch Totalizer Reading xl0 =
gals (if operable)
- d. Cumulative Totalizer Reading Final xl0 = gals (if operable) 44
BwOP WX-501T1 Revision 19 Continuous Use NOTE At low release rates or if Batch and Cumulative inoperable, the gallons released may be Totalizers are calculated by multiplying the percent decrease in tank level by 329 gallons.
G .20. e. RECORD Gallons Released by one of the following:
O TOTALIZER READING gallons Date:_
O (. ~. ) X 329 = gals (Step G.3.a. - Step G.20.b)
Calculation Date:
- f. NOTIFY the Shift Manager that the release is complete.
- g. NOTIFY the Control Room that the release is complete.
Verification is required for stepsNOTE G.21. and G.23. ifORE-PR001 is inoperable and AAR OBwOS RETS 2.1-1a has been initiated.
- 21. VERIFY 0AOV-WX353, Release Tank Discharge Valve to Circ. Water Blowdown, LOCKED CLOSED.
SUPERVISOR VERIFICATION
- 22. RECORD time when key was removed from key lock switch for 0AOV-WX353, Release Tank Discharge Valve to Circ. Water Blowdown.
(N/A if this flowpath was not used)
- 23. VERIFY OAOV-WX896, Release Tank Discharge Valve to Circ. Water Blowdown, LOCKED CLOSED.
SUPERVISOR VERIFICATION
- 24. RECORD time when key was removed from key lock switch for OAOV-WX896, Release Tank Discharge Valve to Circ. Water Blowdown.
(N/A ifthis flowpath was not used)
-25. CLOSE OAOV-WX889 Release Tank 0WX01P Discharge Isolation Valve.
45
BwOP WX-501T1 Revision 19 Continuous Use G. 26. If Relay Block K1 at ORE-PR001 was removed in step G.2., then
- a. NOTIFY Shift Manager that the temporary Electrical Alterations being restored.
- b. REPLACE Relay Block Ki at ORE-PR001, AND SUPERVISOR VERIFICATION C. REMOVE the two placards stating "K1 RELAY REMOVED FOR LIQUID RELEASE", that were placed in Step G.2.c.
- d. If the Electrical Alteration cannot be restored, process a temporary alteration.
- 27. Backflush the OPR01J radiation monitor as follows:
- a. VERIFY release tank OWX01T is less than 96%.
V Do Do not t back thatflush time such the the Radiation release Monitor tank oba level for a period exceeds 97%. of Steps G.27.b. through G.27.n. NOTE may be omitted at OPS Supervisor discretion if ORE-PRO01 is INOPERABLE and AAR-BwOS RETS 2.1-1a has been initiated.
NOTIFY the Control Room that NOTE you will be flushing OPR01J and that they will be receiving an alarm on RM1 1.
- b. VERIFY/OPEN 0WM897, WM Header Isolation Valve
- c. CLOSE 0WX354, Release Tank Discharge to Process Rad Monitor System.
- d. OPEN 0PR052, WX discharge to ORE-PRO01 Sample Connection.
- e. OPEN OPRO50, OPR01J Backflush Isolation Valve 46
BwOP WX-501 T1 Revision 19 Continuous Use G 27. f. OPEN 0WM898, OPR01J WM Supply Header Valve
- g. WAIT 1 minute
- h. CLOSE OPR5004, Skid OPRO1J Flow Isolation Valve FLUSH OPR01J, Radiation Monitor for 15 minutes
- j. CLOSE OPRO50, OPRO1J Backflush Isolation Valve
- m. CLOSE 0PR052, WX discharge to ORE-PRO01 Sample Connection.
- n. OPEN 0WX354, Release Tank Discharge to Process Rad Monitor System
- o. Perform the following:
- 1) OPEN "NO EPN", OPRO1J Return to OWX26T.
- 2) CLOSE "NO EPN", OPROIJ Return to OWX01T.
- 3) Update Placard on Radwaste Control Panel to indicate that OPRO1J is lined up to OWX26T.
- 28. OPS Supervisor: I have reviewed Part G and have verified it is accurate and complete.
OPS Supervisor Date Time 47
BwOP WX-501T1 Revision 19 Continuous Use H. CONTROL ROOM SUPERVISOR RESPONSIBILITY NOTE If the current activity level recorded in step H.1. is greater than 1.31 E-4 pCi/ml, INITIATE a work request to decontaminate the ORE-PROO1 sample chamber.
- 1. RECORD the current reading for ORE-PROO1 (OPSI01).
"pCi/ml Date:
NOTE Step H.2.a. is not required if ORE-PROO1 0BwOS RETS 2.1-1a has been initiated. is inoperable and AAR Step H.2.b. is not required if 0RE-PRO0O is inoperable and AAR OBwOS RETS 2 .1-1a has been initiated.
- 2. SET the Rad Monitor ORE-PROO1 (OPS101) and ORE-PRO10 (OPS1 10) to their original setpoints as follows:
- a. RESET the ALERT Alarm and HIGH Alarm setpoints for ORE-PROO1 (OPS1 01) to their original values by performing the following:
VERIFICATION
- 1) PLACE the RM-11 Console in SUPERVISOR MODE.
- 2) SELECT the ALERT alarm setpoint (channel item 10) to be changed on the ORE-PRO01 (OPS101)
CHAN ITEMS display by KEYING in 10 and DEPRESSING the SEL key. (Following this CHAN ITEM 10 should be displayed in reverse characters.)
- 3) ENTER the original ALERT alarm setpoint USING the format XYZ +/- AB. The CHAN ITEM 10 ALERT Alarm setpoint is 6.56E-5 pCi/ml, enter this as 6.56-5 and DEPRESS the ENTER key. The new value will be displayed after a short delay.
- 4) SELECT the HIGH alarm setpoint (channel item 9) to be changed on the ORE-PROO1 (OPS101) CHAN ITEMS display by KEYING in 9 and DEPRESSING the SEL key. (Following this CHAN ITEM 9 should be displayed in reverse characters.)
48
BwOP WX-501T1 Revision 19 Continuous Use H. 2. a. 5) ENTER the original HIGH alarm setpoint USING the format XYZ +/- AB. The CHAN ITEM 9 HIGH Alarm setpoint is 1.31E-4 pCi/ml, enter this as 1.31-4 and DEPRESS the ENTER key. The new value will be displayed after a short delay.
- b. RESET the ALERT and HIGH setpoints for ORE-PR010 to their original values by performing the following:
VERIFICATION
- 1) SELECT the ALERT alarm setpoint (channel item 10) to be changed on the ORE-PR010 (OPSI
- 10) CHAN ITEMS display by KEYING in 10 and DEPRESSING the SEL key. (Following this CHAN ITEM 10 should be displayed in reverse characters.)
- 2) ENTER the original ALERT alarm setpoint XYZ +/- AB. The CHAN ITEM 10 ALERT USING the format 5.73E-6 pCi/ml, enter this as 5.73-6 Alarm setpoint is and DEPRESS the ENTER key. The new value will be displayed after a short delay.
- 3) SELECT the HIGH alarm setpoint (channel on the ORE-PR010 (OPSI 10) CHAN item 9) to be changed ITEMS display by KEYING in 9 and DEPRESSING the SEL key.
(Following this CHAN ITEM 9 should be displayed in reverse characters.)
- 4) ENTER the original HIGH alarm setpoint USING the format XYZ +/- AB. The CHAN ITEM 9 HIGH Alarm setpoint is 8.19E-6 pCi/ml, enter this as 8.19-6 and DEPRESS the ENTER key. The new value will be displayed after a short delay.
- 5) PLACE the RM-1 1 Console in the NORMAL MODE.
49
BwOP WX-501T1 Revision 19 Continuous Use NOTE DO NOT isolate Circulating Water Blowdown until at least three and one-half (2.§) hours after the release stop time recorded in step G.20.a. to ensure the entire release tank effluent has passed through the Circulating Water Blowdown pipe to the Kankakee River.
Control of Circulating Water Blowdown Flow Limitations may be transferred to an Equipment Status Tag for the purpose of completing this package. The Equipment Status Tag must specify the time and date for completion of the 3.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> flush requirement.
This method is most applicable when performing one day. If control is transferred to an Equipmentmultiple releases in Status Tag, Step H.3. may be marked as "Condition Met".
H 3. 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> or more after the time recorded in step G.20.a., REMOVE the placard stating "Liquid Release in Progress" at OPM01J.
- 4. RECORD the Time and Date "Liquid Release in Progress" placard is removed at OPMOIJ:
Time: Date:
- 5. FORWARD this form to Health Physics to complete Section I.
50
BwOP WX-501 T1 Revision 19 Continuous Use HEALTH PHYSICS SUPERVISION NOTE If a computerized release program is available, you may attach the printout to this form and indicate "see attached" in the calculation spaces in step 1.1. below.
- 1. COMPLETE the table below for each isotope identified in step D.6.a.:
Isotope Total Activity Total Activity Released (pCi
- Isotope Released (pCi)
Sum of activities above =
OBTAIN by multiplying each number in column
- 2 of table in step D.6.a. by total volume released from step G.20.e. (in ml)(ml=gal x 3785)
Total ml released =
ml
- 2. Health Physics Supervision SHALL VERIFY compliance limits, as specified in ODCM Radioactive Effluent with 10CFR50 dose Technical Standard 12.3.2.A, by ENTERING release data into the 10CFR50 ODCM Liquid Release Program per BwRP 6110-8.
(Final) 51
(
BwOP WX-501T2 Revision 3 Reference Use RELEASE TIME TABLE RIVERRIVE FLOW F-O (CFS) MINIMUM
-C-) - -IIURELEASE RE_-AEDRTO (MINUJTES) IURATION , -
S<60 ý-120 121-180 181-240 241400 301-360 361390 391-420 421-450 451-480 481-510 >510
<1100 start after 2330 233 23:0 233 23: 30 0 23:30 23:30 2330 2330 23:30 23:30 start before 07:30 063 05:30 0 0:0 . 03:00 .Q"*30 02:00 01:30 01:00 1100-1300 start after 00:45 0045 00:45 00:45 00:45 00:45 00:45 00:45 - 00:45 00:45 00:45 00:46 start before 08:30 07:30 06:00 0 230L.0djL 04:00 03:30 3:00 . 02:30. 0 1301-1500 start after 02:00 02:00 02:00 02:00 02:00 02:00 02:00 02:00 02:00 02:00 02:00 02:00
! start efoLr 09:45 0 07:45 07:15 06:465 0L;! 05:45 05:15 04:4, 04:15 03:45 03 5 1501-1800 start after 03:15 03:1 03:15 03:15 03:1 03:15 03:15 03:15 03:15 03:15 03:15 03:15
, start before 11:00 1 09:00 1 (WO 07(WO 07:00 WO
- 05 05:00 04 1801-2000 start after 04:00 400 04:00 04:00 04:00 04:00 04:00 04:00 04:00 04:00 04:00 04:00 start before 12:1 1:15 "A
- 1 .2. 09,16 08:45 WAS 07:45 07:15 0jj;4 R 06:15 05:
2001-2400 start after 05:00 0500 0:00 05:00 05:00 050:0 06:00 05:00 05:00 05:00 05:00 05:00 start before 13:00 1 11:00 11.00 10*.00 0:3, 09*00 0: 07:00 06:30 2401-2900 start after 06:00 0 ,00 06:00 06:00 0W0O 06:00 06.-00 06:00 0&-00 06800 06:00 06:00 2401 start before 14:00 :1000 12:030 2 12.1J]0
,0 1100 1.1.0- - I
-- 0&:30 06:00 07:30 2901-3500 start after 07:0 0700 07:00 07:00 07:00 07:00 67:00 07:00 0 7.00C 07:00 07:00 0700 start before 15:00 !
.14: 3:00 01;30 !!:0 10.30 '1000 09:30 09:00 0830 3501-4400 start after 08:00 0800 08:00 08:00 08:00 08:00 08:00 08:00 0&00 08:00 08:00 0 :;
s-tart before t6:00 0 14:00 14:0 4l..:00 30 2:00 !1;30 20:.30 10:00 4401-5600 start after 09:00 0900 09:00 09:00 09:01 00:00 09 0 0:00 'QD:O0 09:00 09:00 0900 start before 17:00 16:015:
0 12;00 5:00 130 11 11:00 10:30 5601-7500 start after 10:00 10:00 10:00 10:00 10:00 10:00 10:00 1000 1000 10:00 10:00 1000 start before 18:00 17:00 16:00 16:00 15:00 14:30 14:00 13:30 13:00 12.30 12:00 11 30
-ý mm m
>7501 start after 11:00 11:0011:00 11:00 11:00 11:00 11:00 110000 10:0 11:00 11:00 1 00 start before 19.00 180 17:00 17:00 16:00 1530 15:00 14:30 14*00 13:30 13:00 1230 (Fk*Q (Rr
Real-Time Data for Kankakee River near Wilmington, 11 (05527500) Page I of 2 Real-Time Data for Kankakee River near Wilmington,,
Ii (0552750Ai}ý Disclahmer.- CW&S 4ata on thus page and suhjeet to nw.ro, 77aýd06~ haeno1cie iecos~p'Vi n~z igWp~WSi wezr n~ njo tnW&iu(~9MrteUie tAtes Goiernmepi aw~ &g ed~iwhefoJ,40F A= e duef~oýW A u- - -e Datafrom other agenciej.w firpAyedfor the collection, checkin&; and Woanais I~nfiormatlo, s only. Mhe 0~3W Is not involved ofother agency data Questions andor with other agency data should be directed to the respective 'commentsconcerning agency More information about the quality of real-time data is.available.
Most recent reading ftabove datuml (di) f above NGVD Retrieve real-time data Please select the type(s) of data and would like for the output. After you the number of days of data you wish to retrieve and the format you have selected the data type3), days please: select Retrieve Data to receive of data, and output format the data.
Data tYpes to retrieve:
g Stage (ft above datum)
E Streaxnflow (cfs)
How many days of data?
m 7days r- 30 days Output format:
SGraph (Tips on retrieving and saving graphs)
Graph size:
g Large Graph r Small Graph Tab-delimited text data file (Tips on retrieving and saving text Date format: data files) http :/1i. water. usgs-gov/nwis-%v/IL/data-components/rtlcg?statnum--05527500 A
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Release Calculation Form Relese at 04/20/2002 3:31 PM ClcultionFormPrinted
- c3E-PROOI1 Uqi~d Eflkent Liquid Release L-02-049 0 Cho* ItORE-PROO Iis in LOCAR I
ReleMaseT* F (talle Tar* per step A.7 Bwacground Calcu~lated Setpoint 6.6-0 Ci/mi 6.83E-05 g&Ci/ml High Setpoint 1-83145 !4.Ci/mi lRebase, number L-2 Alert Selpoint Tank level % 84 1100%
Clrc water nee (cbernistiy MOMse Vohu3"i 1.03E-iOad FAct w/o H-3, NG 1.67E-03 Ci Backrond267-0 pCi/mI Ciwulaw, Setpoint 4.58E-06 ILCihm1 iTn s below Adtam Limit of 0.03 Curies Hligh Suipoint S. 199-6 IaCi/m Rad Releas Rafte 416 Spn Alert Setpoint 5.73F," I&Ci/n Max Releas Rafte 311 gpm Columm 2 j 3 4i 1 Release Duration 78 min As=. Ran. Aing Tank Tech Spec F- -tio Of Afts DWIC Limit Lana FwAction 1104 TI- !J 9.3642 1 100E-02 1 9.13E+00, _i4'iE: I
___________ 10 ____31__ _____ TA0LI 9-05 I -TOTAL I9.62E+00,. 3.60-0 I 04/22002 If.09 _______Cobutne 1 2 1 3 1 4_
Umnraiimd AU.. ati Avung.Tuak Tech Spec Fraction Of Anam DWVC (mahitm) I Activity Limit Fraction Ma-54 9.5A147 _____________9.55E-07 3.OOE-04 3. 1 E-03 1.19E-04 Co-57 6.6914 _______ ___ 6.69E-08 6.OOE-04 1.111-04 4.1 7E-06 CO-511 4.02R-._______ 4.0213-06 2.001-04 2.01E-02 7.52E.04 co-* 1.01145 ______ _ ___ 1.0111-05 3.001-05 3.37E-01 1.261-02 Kr-w 2.49945 _____________2.49E-05 2.OOE-04 1.25E-01I 4.67E-03 Nb-" 3.46147 __________3.4613-07 3.001-04 1.15E-03 4.32E-05~
Te-Ill.. 1.88147 _____________1.31E-07 L.00-04 I .88E-03 7.03E-05 Sb-12S 3.24E-47 _______ ___3.24E-07 3.OOE-04 1.08E-03 4.04E-051
LiquidSj~~
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CURRENT DATE: 20-APR-2002 12:01:10.90 STATION NAME: BRAIDWOOD7L02-049 OWXO1 RELEASE TK (GRAB ONLY) RELEASE
- 049 GENERAL LIQUID RADIONUCLIDE ANALYSISý 7ONFIGURATION FILE ...... : SYS$SYSDEVICE: [CRU. SAMP] 2 1P84 5ASAMP_8 104..NF; 1 3KGbJD SUBTRACTION FILE. :
)ATS:-TIME SAMPLE OBTAINED.......20-APR--2002 10:51:00.00
)ATE-TIME SAMPLE ANALYZED.. .'.: 20-APR-2002 11:09:43.99
'OLLECTOR' S INITIALS... : JRW ANALYST'S. INTTIALS ......... JRW
?ETECTOR SERIAL WM)~~..: 21P845A GEOMETRY TYPE ..............'.:.MRIQ450%
-4ER-GY CALIB GAIN ........: 4.99970E-01 FWHM CALIB .GAIN............ 4.23070E-02 24EP-GY CALIB OFFSET ........ 4.65430E-02 FWHM CALIB OFFSET ........ : 2.08315E-01.
)ETECTOR SERIAL NUMBER. .: 21P845A ENERGY CALIBRATION TYPE..: Daily
- AMPLE CODE....... :RWOWXO1T SAMPLE VOLUME/MASS .......... 4.49690E+02
'AMPLE VOLUME/MASS UNITSi.q SAMPLE POINT...............:
1UCLIDE LIBRARY .IQWýASTE L... 0INTERFERENCE FILE NAME ... :
.OUN'T LIVE TIME ........ . .0:000.00
'OUNT REAL TIME...................... :0 00:50:01.91
'ALIBRATION DATE............ ......... :9-DiEC-1997 09:04:26.93
'EPA.RTMENT............................ S2DB OWX01T EM4ARK...:
IET- COUN4TS (I F CTS= 0, PUT DET 005 AND -CONTACT-MANAGEMENT) .. 2 ANK VOLUME (GALLONS).. ........... : 27636.
ur~iiury of Nuclide Activity Total number of lines in spectrum 11 N~umber of unidentified lines 1 Number of lines tentatively identified by NID 10 90 .91W aclide Type : VALID Wtd M~an Wtd Mean Uncorrected Decay Corr Decay Corr 1-Sigma
.jcl ide H-life Decay UCI/g UCI/g 1-Sigma Error WError Flags
- 4-54 312. 14D 1 .00 9. 548E-07 9.549E-07 1. 127E-07 11.81 D-57 271. 70D 1.00 6. 686E-08 6 .687E-08 2. 836E-08 42.41
)-58 70 .82D 1 .00 4. 019E-06 4 .020E-06 0 .308E-06 7.65 3-60 5. 27Y 1 .00 1 .010E-05 1.0O10E-05 0. 052E-05 5.10 R-85 10. 72Y 1 .00 2. 494E-05 2 .494E-05 1. 149E-05 46.06 3-95 35. 06D 1 .00 3 .462E-07 3 .464E-07 0. 780E-07 22 .52 3,- 123 M 119.70D 1.00 1. 879E-07 1 .879E-07 0.271E-07 14 .44 3-125 2 .76Y 1 .00 3. 238E-07 3 .238E-07 1 .400E-07 43.25 Total Activity : 4.094E-05 4 .095E-05 iclide Type : QIO Wtd Mean Wtd Mean Uncorrected Decay Corr Decay Corr 1- Sigma iclide Hlife Decay UCI/g UCI/g 1-Sigma Error %Error Flags IH-511 100.00y 1.00 0.OOOE+00 0. OOOE+00 0. OOOE+00 0 .00 Total Activity : .OOOE+00 0. OOOE+00 Grand Total Activity 4.094E-05 4. 095E-05
'lags: "K" = Keyline not found "El = Manually edited "M" = Manually accepted "A" = Nuclide specific abn. limit
?ost-NID Peak Search Report Page : 2 3ample ID Acquisition date : 20-APR-2002 11:09:43
[t Energy Area Bkgnd FWHM Channel Left Pw %Err Fit Nuclides 122.25 93 471 0.81 244.42 241 8 41.8 CO-57 0 159.15 256 307 0.77 318.22 315 6 12.5 TE-123M 0 427.58 72 247 1.53 855.12 851 10 42.7 SB-125 9 510.85 664 341 2.40 1021.67 1014 16 7.1 1. 15E+00 ANH-511 9 513.02 68 166 1.31 1026.02 1014 16 45.5 KR-85 0 765.81 148 199 1.58 1531.62 1526 13 21.4 NB-95 0 810.68 1617 181 1.46 1621.37 1616 11 3.0 CO-58 0 834.65 375 200 1.70 1669.31 1664 14 9.5 MN-54 0 1161.36 37 46 0.58 2322.77 2316 11 39.8 0 1173.13 2829 114 1. 80 2346.32 2338 .17 2.1 CO-60 0 1332.44 2533 30 1.81 2664.96 2655 20 2.1 cO-zO
Unidentified Energy Lines Sample ID :
It Energy Acquisition date : 20-APR-2002 Area Bkgnd FWHM Channel Left Pw Cts/Sec %Err 11:09:43
%Eff Flags 1 1161.36 37 46 0.58 2322.77 2316 11 1.22E-02 39.8 5.70E-01 Flags: "T" = Tentatively associated
Nuclide Line Activity Report Page : 4 Sample ID : Acquisition date : 20-APR-2002 11:09:43 S ide Type: VALID Uncorrected Decay Corr 1-Sigma quclide Energy %Abn %Eff UCI/g UCI/g %Error Status 4N-54 834.84 99.98* 7.880E-01 9.548E-07 9.549E-07 11.81 OK Final Mean for 1 Valid Peaks = 9.549E-07+/- 1.127E-07 ( 11.81%)
.0-57 122.06 85.60* 3.248E+00 6.686E-08 6.687E-08 42.41 OK 136.47 10.58 3.316E+00 Line Not Found Absent Final Mean for 1 Valid Peaks = 6.687E-08+/- 2.836E-08 ( 42.41%)
.0-58 810.77 99.40* 8.109E-01 4.019E-06 4.020E-06 7.65 OK 863.93 0.68 7.617E-01 Line Not Found Absent 1674.68 0.52 4.106E-01 Line Not Found Absent Final Mean for 1 Valid Peaks = 4.020E-06+/- 3.077E-07 ( 7.65%)
3-60 1173.24 99.90 5.643E-01 1.005E-05 1. 005E-05 7.32 OK 1332.50 99.98* 5.002E-01 1.015E-05 1.015E-05 7.12 OK Final Mean for 2 Valid Peaks = 1.010E-05+/- 5.154E-07 ( 5.10%)
514.01 0.43* 1. 265E+00 2.494E-05 2.494E-05 46.06 OK Final Mean for 1 Valid Peaks = 2.494E-05+/- 1.149E-05 ( 46.06%)
_O*l 765.79 99.81* 8.576E-01 3.462E-07 3.464E-07 22.52 OK
- -* Final Mean for 1 Valid Peaks = 3.464E-07+/- 7.799E-08 ( 22.52%)
-123M 159.00 84.10* 3.241E+00 1.879E-07 1.879E-07 14.44 OK Final Mean for 1 Valid Peaks = 1.879E-07+/- 2.713E-08 ( 14.44%)
116.95 0.26 3.186E+00 Line Not Found Absent 176.33 6.79 3. 109E+00 Line Not Found Absent 204.13 0.32 2. 854E+00 Line Not Found Absent 208.09 0.24 2.817E+00 Line Not Found Absent 227.91 0.13 2.636E+00 Line Not Found Absent 380.43 1.52 1. 680E+00 Line Not Found Absent 427.89 29.40* 1. 505E+00 3.238E-07 3.238E-07 43.25 OK 443.50 0.30 1.453E+00 Line Not Found Absent 463.38 10.45 1. 394E+00 Line Not Found Absent 600.56 17.78 1. 087E+00 Line Not Found Absent 606.64 5.02 1. 076E+00 Line Not Found Absent 635.90 11.32 1. 028E+00 Line Not Found Absent 671.41 1.80 9. 752E-01 Line Not Found Absent Final Mean for 1 Valid Peaks = 3.238E-07+/- 1.400E-07 ( 43.25%)
,de Type: QIO Uncorrected Decay Corr 1-Sigma Energy %Abn %Eff UCI/g UCI/g %Error Status 511.00 0.00* 1.270E+00 0.000E+00 0.000E+00 0.00 OK Final Mean for 1 Valid Peaks = 0.OOOE+00+/- 0.OOOE+00 ( 0.00%)
3luclide ample IDLine Act ivity Report (continued Acquisition date : 20-APR-2 2ae1:09:4 FPlg: ,,*., 002 11:09:43
= Keyline
Rejected Report Page : 6 Sample ID : Acquisition date : 20-APR-2002 11:09:43 Half-Life Activity 1-Sigma Yvurlide Half -life Ratio Energy %Abund (UCI/g) %Error Rejected by I 2 2.30H 0.32 505.90 5.03 --- Not Found --- Abun.
522.65 16.10 --- Not Found --
630.22 13.70 --- Not Found --
667.72* 98.70 --- Not Found 671.60 5.20 Not Found 727.20 3.20 Not Found 772.60 76.20 Not Found --
809.80 2.90 1.712E-04 12.87 812.20 5.60 --- Not Found --
954.55 18.10 --- Not Found --
1398.57 7.10 --- Not Found --
% Abundances Found = 1.15 (Abn. Limit* 69.00%)
(-134 52.60M 0.83 405.45 7.30 --- Not Found --- Abun.
540.83 7.80 --- Not Found - -
595.36 11.40 --- Not Found --
621.79 10.60 --- Not Found --
677.34 8.50 --- Not Found - -
766.68 4.10 1.473E 05 23.68 847.03* 95.40 --- Not Found --
857.28 6.96 --- Not Found --
884.09 65.30 --- Not Found --
1072.55 15.30 --- Not Found --
1136.16 9.70 --- Not Found --
1806.84 5.70 --- Not Found -- -
% Abundances Found - 1.65 1 "*" = Keyline
Enterference Report 3ample ID Acquisition date : 20-APR-2002Page: 7 11:09:43
.-Jr 'nterference correction performed
MIinimum Detectable Activity Report 3ample ID :
Acquisition date Page : 8
- 20-APR-2002 11:09:43 Bckgnd
., 1.ide Energy MDA Sum (keV) (UCI/g)
%JA 24 8.
-38 1368.63 6.8932E-08
- 1. 1642.42 K-40 16. 2.4031E-07 U-R-41 1460.81 0.OOOOE+00
- 19. 1293.64 2R-51 180. 1.1935E-07
%DN-56 320.08 6.7095E-07 108. 846.76 58SUM 7. 1.6185E-07 FE- 59 1620.00 O.OOOOE+00 134. 1099.25 2_U- 64 6. 3.3441E-07 IJI-65 1345.88 1.2618E-05
- 9. 1481.84
-N- 65 144. 3.8413E-07 IN- 69M 1115.55 3.9053E-07
- E-75 118. 438.63 227. 7.9329E-08 LS-76 136.00 7
.4218E-08 146. 559.08 3R- 82 140. 2.3077E-07 CR-85M 776.52 1.6578E-07 225. 151.19 CR-87 133. 6.5637E-08 CR-88 402.58 2.1086E-07 226. 196.32 UR- 88SE 5. 2.2813E-07 IB- 88 1881.11 O.OOOOE+00
- R-91 1. 1836.00
- 91. 8.4539E-07
"-92 1024.30 4. 7556E-07 206. 934.46
- R-rB-97 95 139. 1. 6342E-06 756.72 2. 4013E-07 152. 657.92
,R-97 121. 1.2650E-07
- 0-99 743.36 1.3587E-07 185. 140.51
- C 9M 185. 4.4323E-08 C 1 140.51 4.5135E-08 G-"r*1OM 162. 306.81 153. 4.5932E-07 N-113 657.76 1.2864E-07 147. 391.70 B-122 114. 1.1154E-07 B-124 564.24 1.3092E-07 B124ESC 153. 602.73 125. 1.1388E-07 B124SUM 669.00 O.OOOOE+00
- 14. 1248.60 E-125M 181. O.OOOOE+00 B-126 109.28 1.5138E-05 124. 666.33 B-126M 1.1160E-07 122. 414.70 k- 131 155. 3.5076E-07
-131 496.31 1.9888E-07 133. 364.48
,-131M 204. 7.9784E-08
-132 163.93 2.2065E-06 129. 667.72
- -132 245. 1.4254E-07 k-133 228.16 6.5587E-08 133. 356.02
-133 123. 1.0166E-07 3-133 529.87 1.0542E-07 168. 81.00 3-133M 214. 1.7535E-07 3-134 233.22 5.3676E-07 156. 604.70
- 134SUM 1. 1.1570E-07 134 1400.00 0.OOOOE+00 135 113. 847.03
- 19. 2.4645E-07
- -135 1260.41 3.3111E-07 190. 249.79
- -135M 127. 6.4070E-08
- -136 526.57 6.5283E-07
- 95. 818.50
!-137 122. 1.1998E-07 661.66 1.2857E-07
- 7. 1435.86 203. 2.0403E-07 165.85 2.6053E-07 149. 537.32 4.0394E-07
4inimum ID Sample Detectable
- Activity Report (continued) Page : 9 Acquisition date : 20-APR-2002 11:09:43 ck3gnf Energy Ir -ide Sum MDA (keVy (UcI/g)
LA---40 7.
BA- 141 1596.18 215.
CE- 141 202.
190.22 6607E- 08
- 7. 4123E-07 4.
7E- 144 145.44 8.6193E-08 175. 133.54
- fF- 181 3. 5019E-07 119. 482.00
,1-187 104. 9.2877E-08 BI-214 685.74 4. 0601E-07 170. 609.32 PB- 214 148. 2. 6457E-07 IP-239 351.90 0. OOOOE+00 311+511 153. 106.12
- 16. 1. 7854E-07 1321.77 O.OOOOE+00 Reviewed by: ___
Date:
JOB PERFORMANCE MEASURE TASK TITLE: Activate the Akergency Response Data Syu*te (33DS).
JPM No.: N-160 REV: 0 TPO No.: IV.F.ZP-04 K&A No.: (2.4.29)
TASK No.: ZP-007 K&A IMP: 2.6 / 4.0 TRAINEE:
EVALUATOR:
DATE:
The Trainee: PASSED this JPM.
TIME STARTED:
FAILED TIME FINISHED:
CRITICAL ELEMENTS: (') 2,3 JPM TIME: _ MINUTES CRITICAL TIME: N/A APPROX COMPLETION TIME 11 MINUTES EVALUATION METHOD:
X PERFORM LOCATION:
IN PLANT SIMULATE X SIMULATOR GENERAL
REFERENCES:
" 1. EP-MW-110-100 "ERO Computer Applicationsw MATERIALS: Copy of EP-MW-I10-100, Attachment 1.
PC with ERe Applications.
TASK STANDARDS:
- 1. Activate the electronic data link (ERDS).
- 2. Demonstrates the use of good Core Work Practices.
TASK CONDITIONS:
- 1. You are an extra NSO.
- 2. The Emergency Response Data System (ERDS) is not yet activated.
INITIATING CUES:
- 1. Plant conditions changed resulting in an upgrade classification from Unusual Event of the Emergency
- 2. The Shift Manager has directed you to Alert.
to activate the Emergency Response System from the NSO desk for Unit Data 1 per EP-MW-110-100, Attachment 1.
Examiner's Note: Do Not allow examine* to select REAL Node. See note next page.
1 N-160 (6/23/01)
ZD73EXAM
PERFORMANCE CHECKLIST STANDARD RECORD START TIME SAT UNSAT N/A Note: To prevent actual activation of the ERDS, when selecting the mode (REAL, SIMULATOR, or the examinee gets to the point of Suite, ask which mode he would EXERCISE) for 3RDB activation select. (Correct answer is REAL). from the GS3P Cue the examinee to select SIMULATOR.
- 1. Refer to EP-MW-110-100, Locate and Open Attachment I.
0EP-MW-I0-100, 0 0 0 Attachment I.
- 2. Refer to EP-MW-110-100, Perform the following Attachment 1. from PC keyboard: 0 o 0 0 START MENU (CUE: Ask which mode "* SITE APPS examinee intends to select prior to "* ERO Applications actual selection, cue the examinee to o ANSWER Question REAL select EXERCISE Mode.)
- SELECT EXERCISE Mode
- 3. Select ERDS Icon.
Perform activate the following to 0 ERDS: 0 0
- SELECT ERDS Icon
- At the next screen, SELECT Braidwood Station.
- Click OK.
- At the next screen, enter the password "SCOUT-.
- Click OK.
- Click box labeled
'Turn On' o Compare the status of ERDS programs on the screen to verify ERDS is on for the appropriate unit(s).
(CUE:) THIS COMPLETES THIS JPM.
RECORD STOP TIME COMMENTS:
N-160 (6/21/01)
ZD73EXAM
TASK CONDITIONS:
- 1. You are an extra NSO.
- 2. The Emergency Response Data System (ERDS) is not yet activated.
INITIATING CUES:
- 1. Plant conditions changed resulting in an upgrade of the Emergency classification from Unusual
- 2. The Shift Manager has directed you Event to Alert.
to Response Data System from the NSO desk activate the Emergency for Unit 1 per EP-MW 110-100, Attachment 1.
N-160 (6/21/01) 3 ZD73EXAM
SIMULATOR SETUP INSTRUCTIONS JPM NO: N-160 REQUIRED SIMULATOR MODE(S): Any MALFUNCTION #'S: N/A COMMENTS:
- 2) Go into the program and select any station but Braidwood.
- 3) When using this JPM multiple times, ensure ERDS is off prior to each start of the JPM. It must be "turned off" with the program button.
4 N-160 (6/21/01)
ZD73EXAM
EI" Exelen n Revision 0 EP-MW-110-100 Page 1 of 26 NudaTl Level 2 - Reference Use ERO COMPUTER APPLICATIONS
- 1. PURPOSE This procedure provides the me(hods for gathering Information for use by the Emergency Response Organization.
- 2. TERMS AND DEFINITIONS 2.1 EXERCISE Mode - The programs under the ERO Applications (EX) groupings draw their data from the plant simulator. Data may be affected by actions of the players in the simulator.
2.2 REAL Mode - The programs under the ERO Applications (Real) grouping draw their data from the actual systems and computer inputs. Data will change as events and operator intervention occurs.
- 3. MAIN BODY NOTES: Computer programs are available for the emergency responder to gather and trend data. This data is essential to enable proper decisions and analysis of events as they occur.
PC login instructions should be available at all ERO computer work stations and will provide guidance on the proper methods available to login to the network.
3.1 To access the ERO set of programs from a Windows networked computer, PERFORM the following:
3.1.1 CLICK on 'Starr in the Windows Task Bar (in the lower left hand comer of the screen) 3.1.2 CLICK on 'Site Apps' 3.1.3 CLICK on ERO Applications' 3.1.4 SELECT either 'Real Mode' or 'Exercise Mode' depending on the data source desired.
3.1.5 SELECT the desired program/category (described below).
3.2 A-MODEL (Within the ERO Applications Dose Assessment folder) 3.2.1 CLICK on the 'A-Model Logins' icon.
3.2.2 CHOOSE the station by clicking in the circle next to the station's name.
EP-MW-110-100 Revision 0 Page 2 of 26 3.2.3 CHOOSE the program by clicking in the circle next to the program name.
REFER to EP-MW-1 10-200, for specific instructions and information on the use of the A-Model program.
3.2.4 CLICK in the 'RUN' box on the bottom of the screen to initiate the selected program.
- 1. ODCSADM - ODCS Administration Program. This program requires a password to enter because it can be used to change the constants and conditions that control how the A-Model menu appears listing all the functions functions. When it is opened a that can be modified. These include:
Core Damage status, factors and rates for calculations, etc.
- 2. Q.DSCAL - View A-Model Screens.
This program can be used to view, not change, the automatic inputs and Model program has. A series of screens the calculated results that the A data. Data can be automatically updated will appear listing the available period. The user should follow the prompts or selected over a specified time from one place to another within the listed on the screen to move program, inputs need to be through the keyboard as the computer's mouse will not work.
- 3. Q.DSCR - Control Room Program.
This program can be used to set Clad Damage conditions, change A-Model clock and time, to check on A-Model status or to re-assign the A-Model automatic output for some stations.
- 4. ODCSPRINT - ODCS Print A-Model Output. This program allows the user to view and /or print the messages and over a period of time. Available dates reports that A-Model generated are shown on the bottom of the screen.
3.3 DAPAR(Within the ERO A lictions Dose Assessmentfolder 3.3.1 CLICK on the DAPAR icon for the applicable station.
3.3.2 REFER to EP-MW-1 10-200, Attachment 2, for specific instructions on use of the DAPAR program.
3.4 C-MODEL(Within the ERO ADlications Dose Assessment folder) 3.4.1 CLICK on the 'C-Model icon.
3.4.2 CLICK on Station and Unit desired.
3.4.3 CLICK on option 3 for Dose Assessment Models. REFER to EP-MW-1 10 200, Attachments 5-8, for specific instructions on use of each of the four C Model programs.
3.4.4 CLICK on further options and respond to the prompts.
EP-MW-110-100 Revision 0 Page 3 of 26 3.4.5 Screens may be printed by going to File: Print.
3.5 Emergency Response Data System (ERDS)
- Refer to Attachment 1 to operate the ERDS application.
3.6 Plant Parameter Display System (PPDS)
- Refer to Attachment 2 to operate the PPDS application. '.
3.7 StationParameter DisplaySystem (SPDS)
A display of selected parameters known as the Safety Parameter Display System is presented. Items such as Rx. level, pressure and power displayed as well as containment are and effluent release status.
NOQTE Normally the current time is displayed, this can be changed using the "Edit" pull-down menu and clicking time and date to be viewed. The on 'Time", then select the "View" pull-down menu ran also be used to customize the display.
3.7.1 CUCK on the 'SPDS' icon.
3.7.2 CLICK on the Unit and station desired.
3.7.3 CLICK on 'OK.
3.8 Plant Status(ERDS Points)
This program will provide data derived The data will reflect current data along from pre-established computer points.
with the computer point ID used to that data. Available groupings of data find include:
3.8.1 CLICK on the 'Plant Status (ERDS Points)' icon.
3.8.2 CLICK on the station desired.
3.8.3 CHOOSE the desired point(s) from the available listings.
- Primary Coolant - shows data on Rx Pressure, level, and power.
- Secondary Coolant - steam generator levels and pressures, (PWRs only)
- Safety Iniection - ECCS flows and aux tank Core Spray) (PWRs; High and Low levels, (BWRs; HPCI, RCIC, Pressure Safety Injection and Boron tank levels).
EP-MW-110-100 Revision 0 Page 4 of 26 Containment - primary containment pressure and temperature, H2 concentration and sump levels (and suppression pool temp. and pressure for BWRs).
Radiation Monitoring - monitored readings forcontainment, effluent and process rad monitors.
- Meteorological - wind speed, wind direction and atmospheric stability.
NOTE: Any or all of the Point History Points displayed in the Program can be launched into Point Trend by either Plant Status single point or, for additional points, clicking on a
- 1. Hold down the 'SHIFT' key and then CLICK on as many points as is desired.
- 2. From. the pull-down menus at the top of the page SELECT Graph.
- 3. , SELECT either 'Selected Points' or 'All Points"
- 4. The selected point history points will then launch into the Point Analysis Trend program.
3.9 Point Analysis Trend This program will display computer point ID data in a graphical format. Up to 24 computer point IDs may be listed, this program contains many options for the user to display and search for data.
3.9.1 CLICK on the 'PointAnalysis Trendc icon.
3.9.2 SELECT the station and unit.
3.9.3 ENTER a known computer point ID or use the Search box to find a computer point ID.
3.9.4 SELECT the date and time for the data display, click in the boxes on the bottom of the screen and enter date and time if different from those listed.
3.9.5 To remove a computer point ID from the listing, CLICK on it once to highlight it, then press the 'REMOVE box.
3.9.6 CLICK either the Excel or Trend box at the bottom of the screen to initialize program.
3.9.7 Search
- 1. After selecting a station and unit, click on the Search box.
EP-MW-110-100 Revision 0 Page 5 of 26
- 2. Click on the "Query" box, a new box will appear with 5 different search categories listed. Selecting any one of these and criteria will create a listing on the bottom of the page entering the search IDs that match the search criteria. The following are with computer points the commonly used search categories:
- 3. Point ID- enter anything you know about the computer point ID number, such as the letter descriptor (AM, R, W) etc. or the (1. 25, 1000) and then click OK or press enterland corresponding number the point IDs corresponding to the search will bedisplayed listing of computer on the bottom of' the screen.
- 4. Description - enter a word or words that may be included in the description of the computer point ID. Click on OK or press enter.
- 5. Engineering Units - either enter the units of the are looking for or use the pull-down arrow next to computer point ID that you the box to identify all the possible units available. Click on OK or press enter.
- 6. When the desired point(s) are identified on the listing on the bottom of the page, double click on each point that you want, (or and observe that it appears in the selected point use the "add" button) screen. When all points are identified, click on OKbox at the top of the and the computer point IDs will be placed on the main screen.
- 7. The pulldown menu "File" can be used to create computer point groupings and call them up later when needed.
- 8. "Open Point" will load computer point IDs that were previously saved to a file location.
- 9. "Save Pointo will bring up a screen asking for the file location to save the grouping to.
3.9.8 Displav
- 1. When all desired computer points (up to 24) are listed on the main screen, click on the 'Trend' box to have the program create the graphical display of the computer points.
- 2. The display is initially one-minute intervals of data over the last three hours. This is set up in rectangular boxes with gridlines, times, dates and the computer point values are all listed.
- 3. The display will automatically update itself as new data is received.
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- 4. If all displays are not shown on the screen, then use the vertical scroll bar to move between the screens. A box at the top of the screen will indicate which display you are viewing out of however many possible.
3.9.9 Editing the Display 1.: Using the "Edit" pull-down menu, the following options are available:
AMode - allows too user to select from Real, Sihulator, Exercise or Test Modes. SE .LJECT either Real or Exercise as appropriate ..
B. Plant - shows a pull-down menu of available stations and units.
C. Start Times - provides a calendar and clock to change the starting times of the display.
D. Interval - normally set to 1 minute, can be changed by the hour or minute to display the data as necessary E. Network Timeout - normally set at 2 minutes as the default.
"2. Using the View" pull-down menu, the following options are available:
A. General Data - when selected displays the rectangular box, dates, times and the graphical display of the data.
B. Math Data - when selected will give the minimum, maximum, average and deviation of the data selected C. Grid Lines - when selected displays the horizontal and vertical gridlines within the box.
D. Slider - Adds a small box below the display box. The Slider box may be moved by single clicking inside the Slider box and holding the mouse button down. While continuing to hold down the mouse button, the Slider box may be moved to the left or right, notice that the value derived the location of the dotted line changes as well.
- 3. Using the "Type" pull-down menu, the data displayed can be shown in various ways from a line graph to a 3D display.
3.10 Point History Help Files The program contains an overview of all of the Point History Programs contained within the GSEP grouping. To get more information program or option within a program, this program can be on any used like a help program to give more details for the user.
EP-MW-110-100 Revision 0 Page 7 of 26 NOTE: Any or all of the Point History Points displayed in the Point Image Program can be launched into Point Trend by either clicking on a single point or, for additional points, hold down the SHIFT key and then click on as many additional points as is desired. Then from the pull-down menus at the top of the page, select Graph, then either Selected points or All points. The selected point history points will then launch into the Point Analysis Trend program.
3.11 Point Ima A.smplifiI one-line diagram is displayed shOwMng4the the selected station. Within the display are various basic steam cycle-for flows, pressures and other measurements that are obtained from computer point IDs. Both-the computer point ID and the data are displayed at various locations along the drawing.
Current data is displayed.
3.11.1 CLICK on the 'Point Image' icon.
3.11.2 CLICK on the unit and station desired.
3.11.3 The executive display shows the Rx Power level and Generator output for each of the nuclear stations in a table format.
3.12 Sianificant Events Lo-a (SEL)
This program allows the user to enter and view the log of significant events that have been created for an event.
- REFER to Attachment 3 for step by step instructions on entering data into the SEL.
3.13 Station Priorities Log (SPL)
The purpose of the SPL is to enhance the communications and the EOF concerning the major station priorities between the TSC TSC has decided on. It shall be the responsibility and activities that the of the TSC to enter station priorities into the SPL. The EOF will view the entries and communicate the information to outside agencies.
- REFER to Attachment 4 for step by step instructions on entering data into the SPL.
3.14 NewsWriter
- Refer to Attachment 5 to operate the NewsWriter application.
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- 4. ATTACHMENTS 4.1 Attachment 1, ERDS Activation 4.2 Attachment 2, Plant Parameter Display System (PPDS) Operation 4.3 Attachment 3, Significant Events Log (SEL) PrOgram Guidance 4.4 Attachment 4, Station Priorities Lol (SPL). Program.
Guidance 4.5 Ataient 5, NeWsWriter Users Guide ..
EP-MW-110-100 Revision 0 Page 9 of 26 ATTACHMENT I ERDS Activation Page 1 of 5 U LI A II I £ u - - . -. -
EIv R I MIIrLP,5L= TO UInton Staton, use Section 3 I NOTE: Activating the ERDS program from the Real Mode wi* send actual plant data to the NRC's Incident Response Center in White Flint, Maryland.
Activating the ERDS program from the Exercise Mode will send exercise data to designated drill computer(s) only.
1.2 SELECT the affected station.
1.3 CLICK 'OK.
1.4 ENTER the Password (Scout) and click on 'OK.
- 2. ERDS ACTIVATION 2.1 CUCK on the box labeled 'Turn On' to activate the program.
2.2 COMPARE the status of the ERDS programs on the screen to plant or PPDS outputs to VERIFY ERDS is on for the appropriate unit(s).
- 3. ERDS TERMINATION 3.1 CLICK on the box labeled 'Turn Off to deactivate the program.
3.2 The program will automatically stop, break the link with the NRC, and stop transmitting data for the unit that is turned off.