ML032460810
| ML032460810 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/21/2003 |
| From: | Berry P Entergy Nuclear Northeast |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-333/03-301 | |
| Download: ML032460810 (184) | |
Text
"Entwgy James A. FitzPatrick Nuclear Power Plant Nuclear Northeast OPERATIONS TRAINING PROGRAMS SRO APPL. TO REV: 0 NEW JPM NUMBER DATE: 5/23/03 TASK TITLE: CANAL DISCHARGE APPROVAL NRC K/A SYSTEM NUMBER: 233 7 113.1 JAF TASK NUMBER:
JAF QUAL STANDARD NUMBER:
ESTIMATED COMPLETION TIME: 20 Minutes SUBMITTED: 1 OPERATION REVIEW:
w APPROVED:
CANDIDATE NAME:
S.S.
NUMBER:
JPM Completion:
(
) Simulated
( X ) Performed Location:
( ) Plant
( X ) Simulator DATE PERFORMED:
TIME TO COMPLETE: -
Minutes PERFORMANCE EVALUATION:
( ) Satisfactory
( ) Unsatisfactory
~~~
~ ~. ~. ~. ~.. ~. ~. ~ _..... ~. ~. ~....... ~ ~ ~..... ~
~
~
~
COMMENTS : (MANDATORY FOR UNSATISFACTORY PERFORMANCE)
EVALUATOR:
SIGNATURE/PRINTED CANDIDATE REVIE W:
SIGNATURE REVIEWED BY:
DOC. COMPLETE:
PROGRAM ADMINISTER Page 1 of 5
JOB PEKbUKMANGk MkA5udk RECORD AND CHECKLIST l-sBQ__
NEW TASK TITLE: CANAL DISCHARGE APPROVAL APPL. TO JPM NUMBER Current Update: 5/23103 By: RWD Date lnt.
Outstanding Items:
Technical Review Additional Information Questions and Answers Validation Procedural Change Required None Comments:
Simulator validated 5/24/03. Any IC Previous Revision Dates:
Page 2 of 5
JOB PtKPUKWNbr rnhkibii; REQUIRED TASK INFORMATION NEW APPL. TO JPM NUMBER TASK TITLE: CANAL DISCHARGE APPROVAL
- 1.
II.
111.
IV.
L.
V.
VI.
SAFETY CONSIDERATIONS A.
Ensure proper safety equipment and safety procedures are observed.
REFERENCES A.
OP-49, LIQUID RADIOACTIVE WASTE SYSTEM, Rev. 51 TOOLS AND EQUIPMENT A.
Calculator SET UP REQUIREMENTS A.
- 8.
C.
D.
E.
Simulator in any operating configuration with tempering gate full closed 17RM-350 data sheet containing background and K-factor is posted at 09-1 1 Operator Aid 446 available in Shift Manager Office Partially completed Canal Discharge Worksheet (OP-49 Attachment 5).
Confirm or correct calculations for current revisions of Op Aid 446 and Liquid Process Monitor Cal Data EVALUATOR NOTES A.
If performing JPM in the plant, inform the candidate that the conditions of each step need only be properly identified and nat actually performed.
- 6.
The candidate should, at a minimum, identify the change in equipment status light indication when equipment operation is simulated.
TASK CONDITIONS A.
B.
Candidate is presented with a partially completed Canal Discharge Worksheet.
Candidate completes worksheet and sets 17RM-350 for canal discharge.
- - CRITICAL STEP L-Page 3 of 5
S/RO/NLO NEW TASK TITLE: CANAL DISCHARGE APPROVAL I.
- 2.
- 3.
VII.
INITIATING CUE STEP STANDARD EVALUATION I COMMENT Select procedure Candidate selects OP-49, Section E.23 SAT / UNSAT SAT / UNSAT
- 7. Liquid rad monitor (17RM-350) background cps
- 8. Liquid rad monitor (17RM-350) K-factor p Ci/m llcps Candidate records 43 from Liquid Process Monitor Cal Data posted at 09-1 1 panel Candidate records 2.09E-7 from Liquid Process Monitor Cal Data posted at 09-1 1 panel SAT / UNSAT You are the Shift Manager. Waste Sample Tank A has been in recycle for the last 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. Complete this Canal Discharge Worksheet and set the radiation monitor in preparation for discharging the sample tank.
- 11. Calculate Canal Dilution Factor
- 6.
- 7.
(CDF):
- 12. Calculate FL:
EVALUILTOR Hand partially completed Canal Discharge Worksheet to candidate.
SAT / UNSAT SAT I UNSAT 5.05E-5 5.05E-3
-~
- a.
- g.
11
- 4.
I 9. Tempering gate/flow %
~
~
~-
~
~~- _
~
SAT / UNSAT
- 13. Calculate Background Correction 5.6E-6 Activitv (BCA) in uCi/ml:
- 14. Calculate HVHi setpoint in pCVrnl:
3.8E-2 SAT / UNSAT I Candidate obtains EPIC value of 0% (EPIC-A-3547) 1
- I 0.
- 11.
- 12.
SAT I UNSAT SAT / UNSAT SAT I UNSAT
- 15. Calculate Hi setpoint in pCVml:
1.9E-2
- 16. Obtain 17RM-350 potentiometer setting for Hi-Hi setpoint from OPAID 446.
- 17. Obtain 17RM-350 potentiometer settina for Hi setDoint from OPAID 446.
8.8 turns SAT / UNSAT 8.4 turns If I
I I
11
- 5.
1 10. Calculate Canal Flow Rate (CFR):
1 396,000 I
SAT / UNSAT Page 4 of 5
STEP STANDARD EVALUATION / COMMENT
- 13.
- 18. Enter potentiometer settings for Hi F ~ A l SAT / UNSAT and Hi-Hi setpoints on Discharge Page 5 of 5
?
I Permit Section B and attach this worksheet to the discharge permit.
Adjust 17RM-350 setpoints Indicate that this activity is complete At panel 09-1 1, candidate unlocks HI and HI-HI Potentiometers and adjusts to 8.4 and 8.8 turns rewectivelv. Candidate re-locks the ootentiometers.
- 14.
ti r
i SAT / UNSAT
LA& -
0 5
- 1.
Number of running circulating water pumps (36P-lA/B/C) d
- 3.
Tank Discnarge Flow Rate (maximum) TDFR 2 c GPT-N m e r of rurming service water pLlIll2s (46P-lA/B/C) 2 2.
-4
- 4.
Tank Activity (ACT) 2-S X pCi/ml (from ciischarge perziz!
OP-49 LIQUID RADIOACTIVE ATTACHMENT 5 Rev. No. 51 WASTE SYSTEM Page 214 of 216 -
NOTE 1:
Items 7 and 8 are obtained at panel 09-14 NOTE 2:
Background should be maintained LESS THAN 1000 cps.
It is recommended that the detector caniscer be ri.ished to levels below this prior to discharge.
cps
- 7.
Liquid rad monitor (17RM-350) background 4 3 n
8.
Liquid rad monitor 0
5.
Tempering gate/flow (ZPIC-A-3547)
CALCULATIONS
- 10. Calculate Canal Flow Rate (CFR)
/
CPR = ( e l x 120,000! i ($2 x 18,000! =
T54cP-,!-)3Q gpm I
(#9 + 100)
- 11. Calculate Canal Dilution Factor - (CDF):
- 12. Calculate F,:
5. 3 S X O
- 13. Calculate Background Correction Activity (BCA) in pCi/ml:
- k c.,,r,tO pCi /ml BCA = (#6 - #7) X #8 = -
L-
- 14. Calculate Hi/Hi setpoint in yCi/rnl:
- 2
- 15. Calculate Hi setpoint in y C i / m l :
CI
- 16. Obtain 17X.K-350 potentiometer secting for F J i - X i sez3,oizz fro>
OPAID 4 4 6.
Hi /Hi PJ 2, 5
ZLuf-r s
- 15. Obtair! 17RV-350 potentiometer setting f o r Hi setpoint from O P X D 4 4 6.
- 18. Enter porentiometer settings for Hi and Hi-Hi sezpoints on Discharge Permit Section B and attach tnis worksheet to che discnarge pernit.
Performed by (SM)
Independent Verification
?rint/Sign/Date Print/Sign/Date COMPLETED FORMS ARE ATTACHED TO THE DISCHARGE PERMIT OP-49 LIQUID RADIOACTIVE ATTACHMENT 5 Rev. No. 51 WASTE SYSTEM
?age 215 of 216 1
w C
a h
n -
5 e,
10 9
8 7
6 5
E z
1 L
(II Liquid Radwaste Effluent Monitor Sample Activity vrs. Alarm Pot Setting 1.OE-1 I
.OE-7 I
.OE-6 1.OE-5
'l.OE-4 1.OE-3 1.OE-2 Sample Activity (uCilml)
(XI NOTE: ---------___--_--_
>> INCREASING ACTIVITY ---------------->>
- ----I I-------
HIGH ALARM POT A HIGH-HIGH ALARM POT Cal Date: 5/13/03 5/?
)I3
Page 1 of 1 MONITOR ID ID #
CAL DATE BACKGROUND K FACTOR CPS uCl/ml CPS RADWASTE LIQUID 17RM-350 5/, 3 / 6 3 73 aJ?qE-7 Y/a9/03 2-2. 3 G i5-7 NORMAL 17RM-351 SERVICE WATER af?
TO CALCULATE ACTIVITY:
DATE POSTED: -5hh3 CHEM TECHNICIAN:
APPROVED,FOR POSTING: yzkzz 1
11 SP-03-07 LIQUID PROCESS RADIATION ATTACHMENT 7 Rev. No. 5 MONITORS Page 57 of 60
- 1.
Number of running circulating water pumps (36P-lA/B/C)., -5
--7 OP-49 LIQUID RADIOACTIVE ATTACXMENT 5 Rev. No. 51 WASTE SYSTEM Page 214 of 216 L-
- 2.
Number of running service water pumps (46P-lA/B/C) 3.
Tank Discharge Flow Rate (maximum) TDFR 2 c; q ; r,
-u 9
4.
Tank Activity (ACT) 3 / 2 LCi/ml (from discharge perzdz!
- 6.
Liquid ra2 moniror (17REI-350) reading 7c C?S (EPIC-A-1209)
NOTE I:
NOTE 2:
Items 7 and 8 are obtained at panel 09-14 Background should be maintained LESS THAN 1000 cps.
It is recommended that the detector caRister be fleshed to levels below this prior to discharge.
cps
- 7.
Liquid rad monitor (17RM-350) backgroun6 8.
Liquid rad monitor (17RM-350) K-factor yCiimllcps
- 9.
Tempering gate/flow (EPIC-A-3547)
CALCULATIONS
- 10. Calculate Canal Flow Rate (CFR)
CFR = (*I X 120,000) + (#2 X 18,000) =
g?m 1 - ( # 9 - 100) i CDF =
TDFR =
- 3
=
CFR
- 10
- 12. Calculate F,:
L-
- 14.
- 15.
- 16.
- 17.
Calculate Hi/Hi Hi/HI =
(ACT) 2 x Calculate Hi Hi =
(ACT) 4 x Fi F.
setpoint in pCi/ml:
$13 2 x $12 setpoint in pCi/ml:
e4
+ #13 4 x #12 Obtain 17W-350 potentiometer OPAID 446.
Obtain 17W-350 potentiometer from ODAID 446.
setting for Hi setpoia:
Hi
- 18. Enter potentiometer settings for Hi and Hi-Hi secpoints on Discharge Permit Section B and attach this worksnee: to the discharge permiz.
Performed by (SM)
Print/Sign/Date Independent Verification Print/Sign/Date COMPLETED FORMS ARE ATTACHED TO THE DISCHARGE PERMIT I,
rl OP-49 LIQUID RADIOACTIVE ATTACHMENT 5 Rev. No.
51 WASTE SYSTEM Page 215 of 216
Enteqy James A. FitzPatrick Nuclear Power Plant Nuclear Northeast OPERATIONS TRAINING PROGRAMS NCEMEASURE SRO NEW-TASK TITLE: EVALUATE SURVEILLANCE TEST APPL. TO JPM NUMBER ACCEPTANCE CRITERIA REV: 0 DATE: 5/23/03 NRC WA SYSTEM NUMBER: 7 7 17 3.013.4 JAF TASK NUMBER:
JAF QUAL STANDARD NUMBER:
ESTIMATED COMPLETION TIME: 20 Minutes SUBMITTED:
OPERATION REVIEW:
APPROVED:
CANDIDATE NAME:
JPM Completion:
( ) Simulated
( )Performed Location:
( ) Plant
( )Simulator c
DATE PERFORMED:
S.S. NUMBER:
TIME TO COMPLETE: -
Minutes PERFORMANCE EVALUATION:
( ) Satisfactory
( ) Unsatisfactory EVAL U AT0 R:
S IG NATU REIPRINTED CANDIDATE REVIEW:
SIGNATURE REVIEWED BY:
DOC. COMPLETE:
PROGRAM ADMINISTER L
Page 1 of 5
I JOB PSKFUKWNCE MEASUKt RECORD AND CHECKLIST NEW TASK TITLE: EVALUATE SURVEILLANCE TEST ACCEPTANCE CRITERIA APPL. TO JPM NUMBER Current Update: 5/23/03 By: RWD Date Int.
Outstanding items:
Technical Review Additional Information Questions and Answers Procedural Change Required Validation None Comments:
Previous Revision Dates:
Page 2 of 5
JUE PtKtUKfUbc nhr~burrt REQUIRED TASK INFORMATION NEW TASK TITLE: EVALUATE SURVEILUNCE TEST ACCEPTANCE CRITERIA APPL. TO JPM NUMBER
- 1.
SAFETY CONSIDERATIONS A.
Ensure proper safety equipment and safety procedures are observed.
II.
REFERENCES A.
- 9.
AP-19.01, SURVEILLANCE TESTING PROGRAM C.
AP-03.11, OPERABILITY AND REPORTABILITY DETERMINATIONS ST-01 B, MSlV FAST CLOSURE TEST 111.
TOOLS AND EQUIPMENT A.
None IV.
SET UP REQUIREMENTS A.
B.
Best if conducted in the Control Room or the simulator.
If performed in alternative locations, normal controlled references and prints may need to be available.
L-.
V.
EVALUATOR NOTES A.
If performing JPM in the plant, inform the candidate that the conditions of each step need only be properly identified and nat actually performed.
- 9.
The candidate should, at a minimum, identify the change in equipment status light indication when equipment operation is simulated.
VI.
TASK CONDITIONS A.
- 9.
Candidate will review a completed ST-01 B Surveillance Test containing test failure data that was nor recorded by the performer or SNO
- - CRITICAL STEP L-Page 3 of 5
i' SlROlNLO TASK TITLE:
VII.
INITIATING CUE You are the Control Room Supervisor. The SNO has just completed ST-OIB, MSIV FAST CLOSURE TEST, and forwards it to you to complete the management SRO review.
EVALUATnR Hand copy of completed Surveillance Test to candidate.
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
STEP 11.2.1 Verify data is within required tolerances.
11.2.2 Verify data attachments, such as recorder printouts and calibration sheets are included as required.
11.2.3 Verify required initials and signatures have been entered.
11.2.4 Review test to determine if test results satisfy acceptance criteria:
(J Satisfactory (J Satisfactory with corrective actions 11.2.5 IF Level 1 acceptance criteria is not satisfied, THEN immediately notify Operations Manager or alternate.
Record name of person notified.
1 Unsatisfactorv 1 I
.2.6 Initiate required corrective and compensatory actions.
(J Not required (J Required STANDARD Candidate review all data recorded in Surveillance Test.
Candidate may determine that step 8.6.3 does not meet acceptance criteria.
This step is not applicable to this test.
Candidate review all initiakignature blocks for completion Candidate will recognize that step 8.6.3 does not meet acceptance criteria and therefore check the Unsatisfactory box Candidate will make the required notification EVALUATOR Receive and acknowledge the notification Candidate will indicate the need to complete a Tech Spec review, Condition Report and PID and check the Required box.
EVALUATOR ReDort to candidate that all are in progress.
~~
~
~
EVALUATION / COMMENT SAT / UNSAT SAT I UNSAT SAT / UNSAT SAT / UNSAT SAT / UNSAT SAT / UNSAT Page 4 of 5
S/RO/NLO STEP STANDARD
- 7.
I I
.2.7 Sign and record date and time.
Candidate will sign, date and time the surveillance test i
EVALUATION I COMMENT 1
SAT / UNSAT Page 5 of 5
ENTERGY NUCLEAR OPERATIONS, INC.
JAMES A. FITZPATRICK NUCLEAR POWER PLANT OPERqTIONS SURVEILLANCE TEST PROCEDURE MAIN TURBINE BYPASS VALVE CYCLE TEST ST-21Q REVISION 0 APPROVED BY: 4
~ESPON$IBLE PR EFFECTIVE DATE:
DATE JCZ FIRST ISSUE FULL REVISION 0 LIMITED REVISION 0 CONTINUOUS USE TSR TECHNICAL 3
'. 7,,
MAIN TURBINE BYPASS VALVE CYCLE 'i'ES'Y ST--L&
TABLE OF CONTENTS SECTION 1.0 REQUIREMENTS 2.0 PURPOSE...................
3.0 REFERENCES
4.0 PREREQUISITES................
5.0 TEST EQUIPMENT, SPECIAL TOOLS, AND MATERIALS 6.0 PRECAUTIONS AND LIMITATIONS.........
7.0 GENERAL TEST METHODS 8.0 PROCEDURE..................
8.1 Main Turbine Bypass Valve Testing While Shutdown in Cold Condition 1
b 7
E 9.0 RETURN TO NORMAL
................... 10 10.0 ACCEPTANCE CRITERIA..................
10 11.0 ACCEPTANCE VERIFICATION................
11 12.0 ATTACHMENTS......................
14
- 1. TEST SIGNOFF LOG 15 Rev. No. 0 Page 3 of 15
S I - - ? - ?
MAIN TURBINE BYPASS VALVE CYCLE TEST u -.-&k NOTE:
Sections 4 and 5 may be performed ir? an17
&XI::
7
L order or concurrently.
NOTE: This test is to be performed as directed from OD-S; Section D. 2.
in OP-9 Section D.2 Required prerequisites are established 4. 0 4. 1 4. 2 4. 3 4. 4 4.5 4. 6 4. 7 5.0 5.1 5. 2 PREREQUISITES SM has granted permission to perform this test.
Revision Number of this Working Copy is the same as the revision number listed in the Master Copy of the Index of Operations Surveillance Test Procedures.
Test personnel have read this procedure and are thoroughly familiar with its contents.
EHC Section (Panel 0 9 - 5 ) Lamp Test has been completed per Subsection G.2 of OP-9.
Start of test recorded.
Date / Time Start of test recorded in NCC Log Book.
Reactor is in Mode 4.
TEST EQUIPMENT, SPECIAL TOOLS, AND MATERIALS Test Equipment None Special Tools None 5. 3 Materials None R e v. No. 1 Page 5 of 15
MAIN TURBINE BYPASS VALVE CYCLE TEST Sl-"li^
7.0 GENERAL TEST METHODS 7.1 The main turbine bypass valves will be cycled one a:
2 time from the panel and observed locally for proper operaziox.
This test will be performed in conjunction wlch OF-:
D.2, Main Turbine Valve Testing While Shutdown ir Cel5 Condition.
7.2 Secz:on 7.3 This procedure may be used for post-work testing and verification of operability for applicable eqclpment gro\\-iae5 the following actions are performed:
7.3.1 The actions and requirements of Sections 1 throuc'n 6, 10, and 11 are satisfied.
7.3.2 The applicable portions of Sections 8 and 9 are performed.
7.3.3 Signoffs for non-applicable portions of Seccions 6 and 9 are marked "NA". Non-applicable subsections may be marked "NA" by drawing a diagonal line on each page and marking the page "NA".
7.3.4 The reason for partial performance of this test is documented in Subsection 11.3.
c Rev. No. 1 Page 7 of 15
S'L'-L l<\\
MAIN TURBINE BYPASS VALVE CYCLE TEST L-'
8.1.4 Test BPV-3 as follows at BYP VLV TEST section:
A. Depress and hold SELECT BPV-3 pushbuttoz. i-)
B. Verify BPV-3 opens at moderate speed until 85 to 95% open, then fast opens to full open.
C. Release SELECT BPV-3 pushbutton.
(-)
D. Verify BPV-3 closes smoothly to full closed.
E. Verify READY TO SELECT light comes on.
(-1 8.1.5 Test BPV-4 as follows at BYP VLV TEST section:
A. Depress and hold SELECT BPV-4 pushbutton. (-)
B. Verify BPV-4 opens at moderate speed until 85 to 95% open, then fast opens to full open.
C. Release SELECT BPV-4 pushbutton.
(-1 D. Verify BPV-4 closes smoothly to full closed.
E. Verify READY TO SELECT light comes on.
(-)
8.1.6 WHEN main turbine bypass valve testing is complete, perform the following at BPV VLV TEST section:
A. Depress OFF pushbutton at BYP VLV TEST section.
(-1 B. Verify READY TO SELECT light goes o f f.
(-1 Rev. No.
Page 9 of 15
MAIN TURBINE BYPASS VALVE CYCLE YEST b--L.-Q 11.0 ACCEPTANCE VERIFICATION 11.1 NCO/SNO Review 11.1.1 Verify required data has been recorded and is ~ i t ~ i ~.
required tolerances.
Verify required initials and signatures nave beeE entered.
11.1.2 11.1.3 Review test to determine if test acceptance criteria has been satisfied.
11.1.4 Check one of the following as appropriate for test results:
(-1 Acceptance criteria satisfied, no corrective action required.
(-1 Acceptance criteria satisfied, corrective action required.
(-)
Acceptance criteria not satisfied.
IF acceptance criteria is satisfied AND corrective action is required, THEN perform the following:
11.1.5 A. Describe in Subsection 11.3, Remarks.
B. Initiate a PID and record PID number.
PID Number 11.1.6 IF acceptance criteria is not satisfied, THEN perform the following:
A. Immediately notify SM.
B. Initiate a PID and record PID number.
PID Number 11.1.7 Sign and record date and time SNO or NCO Rev. No. 0 Date/Time Page 11 of 15
11.3 Remarks Rev. No.
Page 13 of 1 5
TEST SIGNOFP LOG PRINTED NAME INITIALS DATE:
DOSE i-:OV2S R EC S I 1-Z I:'O RXS?
~
~
~
-~
~~
I Total Man-Hours Rev. No. 1 Page 15 of 15
LCO INDEX A?-12-08 LCO TRACKING AND SAFETY FUNCTION DETERMINATION PROGRAM ATTACHMENT 2 R e v. N o. 3 Page 41 of 49
1 DATE:
2 TIME:
3 % PWR 4 MODS:
8 CR NO.
1 Y P'IU/WK NU.
10 CONDITION INITIATING LCO: Planned Unplanned Other I
I I
__,.___^
~
11 CONDITION 15 LCO 3. C. 6 EhTERED 1 6 LOSS OF SAFETY FUNCTION
[3 YES NO 0 NA 17 CRS:
18 SM:
CLOSEOUT 19 LCO RESTORED DATE/TIME 20 COMMENTS/CORRECTIVE ACTIONS I
14 COPIPLETE PAGE ACTION :
4 1 2 2 SM:
21 CRS:
12 REOUIRED ACTION 13 COMPLETYON TIE Required by:
Date:-/-/-
Time :
Required by:
Date:-/-/-
Time :
Required by:
Date:
/
/-
Time :
~~
~
Completed :
Date:-:-/-
Time :
Initials :
Compieced:
Dace:
I i-Time :
Initials :
Compieted:
Date:-!-/-
Time :
initials :
RECORD NAME/DEPAR"T NOTIFIED IF OTHER THAN OPS REQUIRED TO COMPLETE This a Quality Record u
AP-12.08 LCO TRACKING AND SAFETY FUNCTION DETERMINATION PROGRAM ATTACHMENT 1 Rev. No. 3 Page 37 of 49
z,rn T ~ A C K T N G s y ~ E 2 1 ExP4 - 2.10 Tracking NO.
TS/TRM/ODCP'!
No.:
'3NI)ITION INITIATING LCO:
REQUIRED ACTION:
COMPLETION TIME (Frequency):
RESPONSIBLE DEPARTMZN?:
L/
Date T i m e / In5 t
/
i
/
/
This a Quality Record
/
i
/
/
/
/
i, AP-12-08 LCO TRACKING AND SAFETY FUNCTION DETERMINATION PROGRAH ATTACHMENT 1 Rev. No. 3 Page 38 of 4 9
Description Document
?ID/WR/CR/ST I
-1 O?EX 2 L C S 3 D a t e 'TxRe Daze ":me i
i I
1 I
I I
I I I
I I
AD-12.08 LCO TRACKING AND SAFETY FUNCTION DETERMINATION PROGRAM ATTACHMENT 1 Rev. N o. 3 Page 2 of 4 9 L
This a Quality Record L,
i t I
4
?acre AP-12-08 LCO TRACKING AND SAFETY FUNCTION DETERMINATION P R O G M ATTACHMENT 1 Rev. No. 3 Page 40 of 49
.I c -
Continuatioz Sheer This Is a Quality Record
\\ /
1
V ENTERGY NUCLEAR OPERATIONS, INC.
JAMES A. FITZPATRICK NUCLEAR POWER P m
OPERATIONS SURVEILLANCE TEST P R O O W M B I V FAST CLOSURE TEST (IST)
ST-18 RgvISIOa 23 APPROVED BY:
EFFECTIVE DATE :
( D - I q - 0 2 FIRST ISSUE 0 FULL REVISION 0 LIMITED REVISION f
- * * * * * * * * * * * * * *
- t i * * * * * *
- TSR CONTINUOUS USE TECHNICAL
ST-1B MSIV FAST CLOSURE TEST (IST)
REVISION
SUMMARY
SHEET REV. NO.
CHANGE AND REASON FOR CHANGE 23 22 21 20 Added clarification to frequency that valves tested at a cold shutdown frequency may include valves tested while decreasing power to cold shutdown or while increasing power to steady state power operation (NUREG-1482 Section 3.1.1.1 supporting PCR dated 5/16/02)
Revised prerequisites to change plant condition to Rx Pressure
< 5psig to allow testing prior to cold shutdown to minimize MSIV dry stroking (PCR dated 5/16/02)
Revised prerequisite on water level to include option of New GE REM Steam line plugs installed and steam lines drained, allows performance earlier in outage(PCR dated 4/19/02)
Revised Section 8 and Section 9 to include provisions for MSIVs remaining closed per OP-65 (PCR dated 5/16/02)
Revised prerequisite to refer to Reactor Mode for support Of I T S.
Made changes to the Operations Department Operating Shift Organization titles per FYI #02-005 throughout. Changes not rev barred.
Deleted the requirement to record calibration due date in Sections 4 and 5 per ODSO-31.
Revised Section 11 to eliminate SM and Assistant Operations Manager review and replaced with one review by a Management SRO. This change reduces the administrative burden of multiple independent reviews. Change made with Rev. 23 to AP-02.01.
Revised Section 1.2 to include Improved Technical Specification references.
Deleted Tech Spec frequency of quarterly and updated Tech Spec surveiliance references in Subsection 1.2.1 to reflect Tech Spec Amendment 242. (PCR #1 dated 2/24/99)
Full revision to reflect change to IST program to perform MSIV fast closure at Cold Shutdown. Also deleted testing of 29MOV-74 and 29MOV-77 (relocated to ST-1C) and updated procedure title.
Rev. No. 23 Page 2 of 24
MSIV FAST CLOSURE TEST ( I S T )
ST-1B TABLE OF CONTENTS c-
\\--
SECT ION 1.0 REQUIREMENTS 2.0 PURPOSE..........................
3.0 REFERENCES
4 6
6 7
8 4.0 PREREQUISITES.......................
5.0 TEST EQUIPMENT, SPECIAL TOOLS, AND MATERIALS 8
6. 0 PRECAUTIONS AND LIMITATIONS................
7.0 GENERAL TEST METHODS 10 8.0 PROCEDURE.........................
I1 8.1 MSIV 29AOV-80A Test....................
11 8.2 MSIV 29AOV-86A Test....................
11 8.3 MSIV 29AOV-80B Test..................,.
12 8.4 MSIV 29AOV-86B Test....................
12 8.5 MSIV 29AOV-80C Test....................
1 3 8.6 MSIV 29AOV-86C Test....................
13 8.7 MSIV 29AOV-80D Test....................
14 8.8 MSIV 29AOV-86D Test....................
14 9. 0 RETURN TO NORMAL 15 10.0 ACCEPTANCE CRITERIA....................
18 11.0 ACCEPTANCE VERIFICATION..................
1 9 12.0 ATTACHMENTS........................
23
- 1.
TEST SIGNOFF LOG 24 Rev. No.
2 3 Page 3 of 24
ST-1B MSIV FAST CLOSURE TEST ( I S T )
1.0 REQUIREMENTS 1.1 Frequency
?COM1.4.1 I S T cold shutdown testing shall be performed as follows:
Valve exercising shall commence within 4 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of achieving cold shutdown, and continue until all testing is complete or the plant is ready to return to power.
Completion of a l l cold shutdown testing is not a prerequisite to plant startup, provided testing began within 4 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of achieving cold shutdown. Any testing not completed during one cold shutdown shall be scheduled first during the next cold shutdown.
For extended outages, testing need not begin within 4 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided all valves that are required to be tested during cold shutdown are tested before plant startup.
Valves tested at a cold shutdown frequency may include valves tested while decreasing power to cold shutdown or while increasing power to steady state power operation.
Cold shutdown tests are not required if satisfactorily completed within the past 3 months (92 days).
L--
Cold shutdown tests shall be completed before startup from a Refueling Outage, unless test has been completed within the past 3 months (92 days).
Rev. No. 23 24 Page 4 of
1.2 Technical Bsmcificati-1.2.I
~ i l l a a c 0 RsquirarPernt.
SR 3.6.1.3.6 m: SR 3.6.1.3.7 is satisfied by completion of ST-1B and ST-1D.
Partially satisfies SR 3.6.1.3.7 1.2.2
&imiting CaPaitiaPa for Operation LCO 3.6.1.3 1.3 m o r ASME Section XI 1989 Edition no addenda 1.4.1 JAFNPP Inservice Testing Program for Pumps and Valves, Cold Shutdown Justification CSJ-018 defers testing of MSIVs to cold shutdown.
1.5 -etatione None Rev. No. 23 Page 5 of 24
ST-1B MSIV FAST CLOSURE TEST (IST) 2.0 3.0 3.1 3.2 PURPOSE To test MSIVs as required by the IST Program.
REFERENCES Performance References None Developmental References 3.2.1 3.2.2 3.2.3 3.2.4 3.2.5 3.2.6 3.2.7 3.2.8 3.2.9 3.2.10 3.2.11 3.2.12 ODSO-32, Shutdown Procedure OP-1, Main Steam System ASME Section XI 1989 Edition no addenda Inservice Testing Program For Pumps and Valves, Third Interval AP-19.05, Pump and Valve Inservice Testing ESK-7A, 7B FM-29A 1.67-97 thru 98 1.70-98 thru 110 AP-01.04, Tech Spec Related Requirements, Lists and Tables NUREG-1482 Guidelines for Inservice Testing at Nuclear Power Plants, Section 3.1.1.1 JD-01-123, GE REM Light Dryer Wet Transfer System Rev. No.
23 Page of 24
ST-1B MSIV FAST CLOSURE TEST (IST)
NOTE:
Sections 4 and 5 may be performed in any order or concurrently.
4.0 4.1 4.2 4.3 4.4 4.5 4.6 4. 7 4.8 4.9 PREREQUISITES SM has granted permission to perform this test.
Revision Number of this Working Copy is the same as the revision number listed in the Master Copy of the Index of Operations Surveillance Test Procedures.
Test personnel have read this procedure and are thoroughly familiar with its contents.
Start of test recorded.
Tcoil.(
I S -;hj t i c l o
'Date/Time -
Start of test recorded in SNO Log.
CCTSl Reactor is shutdown, Reactor Pressure c 5 psig.
[ITS1 Reactor is in Mode 3, 4 or Mode 5, Reactor Pressure e 5 psig.
RPV Water Level is LESS THAN 270 inches or GE REM Main Steam Line plugs installed with steamlines drained.
Calibration for each instrument listed in Subsection 5.1 is up-to-date.
IF ST-41D, Remote Valve Position Indication Verification (IST), is in progress, THEN performance of this test has been coordinated with the performance of ST-41D.
k';
Rev. No. 23 Page 7 of 24
MSIV FAST CLOSURE T E S T (IST)
S T - 1 B L-5.0 TEST EQUIPMENT, SPECIAL TOOLS, AND MATERIALS 5.1 Test Equipment Stopwatch cc I Serial Number 5.2 Special Tools None 5.3 Materials None 6.0 PRECAUTIONS AND LIMITATIONS 6.1 Precautions None 6.2 Limitations 6.2.1 Test personnel shall immediately notify the SNO or CRS of any failure to meet acceptance criteria.
6.2.2 Test personnel shall print name, sign initials, and enter date on Attachment 1 before performing Section 8 of this test.
6.2.3 When test personnel complete their assigned portion of this test, they shall enter hours worked on.
6.2.4 Once this test has been started, any additional test personnel shall read this procedure and become thoroughly familiar with its contents before performing any portion of this test.
Rev. No. 23 Page 8 of 24
ST-1B MSIV FAST CLOSURE TEST ( I S T )
6. 2. 5 Multiple working copies of this test may be used provided the following requirements are satisfied:
NOTE:
The work site is defined as the location where work is controlled. The location of the work site is at the discretion of the SNO.
A. A working copy of this test shall be retained at the work site.
B. The work site working copy shall be the legal record for documenting this test.
C. Data from all steps performed away from the work site, including signatures, initials, and recorded values, is transcribed into the work site working copy following completion of test.
6. 2. 6 Conditional (IF, THEN) steps in this test may be marked IINAII if not applicable.
6.2.7 Steps in this test marked *'NRt1 are not required to be initialed.
Rev. N o.
23 Page 9 of 24
ST-1B MSIV FAST CLOSURE TEST (IST) 7.0 7.1 7.2 7.3 7.4 GENERAL TEST METHODS This test consists of eight subsections which test MSIVs as required by the IST Program.
Subsections 8.1 through 8. 8 may be performed in any order as necessary to facilitate plant operations or maintenance.
Steps within each subsection shall be performed in the order specified.
Valve closing times are measured from when the control switch is placed in close until the red open indicating light goes off. IST limits are listed as (IST:). Tech Spec time limits are listed as (TS:).
This procedure may be used for post-work testing and verification of operability for applicable equipment provided the following actions are performed:
7.4.1 The actions and requirements of Sections 1 through 6, 10, and 11 are satisfied.
7.4.2 The applicable portions of Sections 8 and 9 are performed.
7.4.3 Signoffs for non-applicable portions of Sections 8 and 9 are marked IsNA1*.
Non-applicable subsections may be marked IsNAss by drawing a diagonal line on each page and marking the page lsNA1l.
7.4.4 The reason for partial performance of this test is documented in Subsection 11.4.
+-
Rev. NO. 23 Page 10 of 24
ST-1B Init 8.0 PROCEDURE 8.1 MSIV 29AOV-80A Test 8.1.1 Record as-found position of MSIV 29AOV-80A.
ObUJ (pos'it ion) 8.1.2 Ensure open MSIV 29AOV-80A.
8.1.3 Close and time MSIV 29AOV-80A.
Closing time 7
secs
( I S T : 3 to 5 secs)
(TS: 3 to 5 secs) 8.1.4 IF desired to have valve remain closed per Section F of OP-65, THEN mark the following step (N/A).
8.1.5 Ensure MSIV 29AOV-80A is in the as-found position recorded in Step 8.1.1.
8.2 MSIV 29AOV-86A Test 8.2.1 8.2.2 8. 2. 3 8.2.4 8.2.5 Rev. No. 23 Record as-found position of MSIV 29AOV-86A.
c l o s d (pos it ion)
Close and time MSIV 29AOV-86A.
Closing time 4- \\
secs (IST: 3 to 5 secs)
(TS: 3 to 5 secs)
IF desired to have valve remain closed per Section F of OP-65, THEN mark the following step (N/A).
Ensure MSIV 29AOV-86A is in the as-found position recorded in Step 8.2.1.
2 24 Page 11 of
L' ST-1B MSIV FAST CLOSURE TEST (IST)
Init 8.3 MSIV 29AOV-80B Test 8.3.1 Record as-found position of MSIV 29AOV-80B.
(.if?
TkI (posit ion) 8.3.2 Ensure open MSIV 29AOV-80B.
8.3.3 Close and time MSIV 29AOV-80B.
Closing time 1 secs (IST: 3 to 5 secs)
(TS: 3 to 5 secs) 8.3.4 IF desired to have valve remain closed per Section F of OP-65, THEN mark the following step (N/A).
8.3.5 Ensure MSIV 29AOV-80B is in the as-found position recorded in Step 8.3.1.
8.4 MSIV 29AOV-86B Test 8.4.1 8.4.2 8.4.3 8.4.4 8. 4. 5 Rev. No. 23 Record as-found position of MSIV 29AOV-86B.
CIcJild (posit ion)
C l o s e and time MSIV 29AOV-86B.
Closing time 3
- 3 secs (IST: 3 to 5 secs)
(TS: 3 to 5 secs)
.Y f,
IF desired to have valve remain closed per Section F of OP-65, THEN mark the following step (N/A).
Ensure MSIV 29AOV-86B is in the as-found position recorded in Step 8.4.1.
Page 12 of 24
ST-1B MSIV FAST CLOSURE TEST (IST)
Init 8.5 MSIV 29AOV-80C Test 8.5.1 Record as-found position of MSIV 29AOV-80C.
(posit ion) 8.5.2 Ensure open MSIV 29AOV-80C 8.5.3 Close and time MSIV 29AOV-80C.
closing time
- 2. 7 secs (IST: 3 to 5 secs)
(TS: 3 to 5 secs) 8.5.4 IF desired to have valve remain closed per Section F of OP-65, THEN mark the following step (N/A).
8.5.5 Ensure MSIV 29AOV-80C is in the as-found position recorded in Step 8.5.1.
8.6 EdSIV 29AOV-86C Test 8.6.1 8.6.2 8.6.3 8.6.4 8.6.5 Rev. No. 23 Record as-found position of MSIV 29AOV-86C.
Close and time MSIV 29AOV-86C.
Closing time s - 1 secs (IST: 3 to 5 secs)
(TS: 3 to 5 secs)
IF desired to have valve remain closed per Section F of OP-65, THEN mark the following step (N/A).
Ensure MSIV 29AOV-86C is in the as-found position recorded in Step 8.6.1.
v Page 13 of 24
'U' 8.7 MSIV 29AOV-80D T e s t Init 8.7.1 Record as-found position of MSIV 29AOV-80D.
8.7.2 Ensure open MSIV 29AOV-80D 8.7.3 Close and time MSIV 29AOV-80D.
Closing time
- 3. 5 sees (IST: 3 to 5 secs)
(TS: 3 to 5 secs) 8.7.4 IF desired to have valve remain closed per Section F of OP-65, THEN mark the following step (N/A).
8.7.5 Ensure MSIV 29AOV-80D is in the as-found position recorded in Step 8.7.1.
8.8 MSIV 29AOV-86D T e s t 8.8.1 Record as-found position of MSIV 29AOV-86D.
8.8.2 Ensure open MSIV 29AOV-86D.
8.8.3 Close and time MSIV 29AOV-86D.
Closing time 41 S-secs (IST: 3 to 5 secs)
(TS: 3 to 5 secs) 8.8.4 IF desired to have valve remain closed per Section F of OP-65, THEN mark the following step (N/A).
8.8.5 Ensure MSIV 29AOV-86D is in the as-found position recorded in Step 8.8.1.
n Rev. No. 23 Page 14 of 24
ST-1B 9.0 RETURN TO NORMAL 9.1 System Restoration 9.1.1 IF MSIVs remained closed per OP-65 Section F, THEN each MSIV is closed:
MSIV 29AOV-80A MSIV 29AOV-86A MSIV 29AOV-80B MSIV 29AOV-86B MSIV 29AOV-80C MSIV 29AOV-86C MSIV 29AOV-80D MSIV 29AOV-86D 9.1.2 IF MSIVs were not closed per OP-65 Section F, THEN each MSIV is in the as-found position recorded in the specified step:
MSIV 29AOV-80A is in the position recorded in Step 8.1.1 MSIV 29AOV-86A is in the position recorded in Step 8.2.1 MSIV 29AOV-80B is in the position recorded in Step 8.3.1 MSIV 29AOV-86B is in the position recorded in Step 8.4.1 MSIV 29AOV-80C is in the position recorded in Step 8.5.1 MSIV 29AOV-86C is in the position recorded in Step 8.6.1 MSIV 29AOV-80D is in the position recorded in Step 8.7.1 MSIV 29AOV-86D is in the position recorded in Step 8.8.1 Init di R Rev. No. 23 Page 15 of 24
- -. I -~~
S T - 1 B MSIV FAST CLOSURE TEST ( I S T )
9. 1. 3 I F all MSIVs are open, THEN the following MSIV CLOSURE T R I P relays are energized 5A-K3E at panel 5A-K3A at panel 5A-K3C at panel 5A-K3G at panel 5A-K3F at panel 5A-K3B at panel 5A-K3D at panel 5A-K3H at panel 09-15 0 9 - 1 5 0 9 - 1 5 0 9 - 1 5 09-17 09-17 09-17 09-17 9.1.4 Steps 9. 1. 1 through 9. 1. 3 verified by Licensed Operator.
Rev. No.
23 Page 16 of 24
ST-1B Init 7
9.2 Review and Signoff
.C I
n 9.2.1 Test completed. 1 S ; 0 4 c ( 1 L -1w Date/T!irde 4
9.2.2 Test personnel have recorded hours worked on.
9.2.3 Man-Hours totalled and recorded on.
Rev. NO. 23 Page 17 of 24
ST-1B IST Stroke Time Tech Spec Valve (secs)
Stroke Time (secs) 10.0 ACCEPTANCE CRITERIA step 10.1 Level 1 Acceptance Criteria 2 9AOV-8 OB 3 to 5 3 to 5 2 9 ~ 0 ~ -
a 6 ~
3 to 5 3 to 5 2 9 AOV - 8 0 C
3 to 5 3 to 5 0
Each tested valve was cycled and closed within the following stroke time limits:
8.3.3 8.4.3 8.5.3 2 9AOV-8 6D 3 to 5 1
3 to 5 3 to 5 1
8.1.3 I
3 to 5 8.8.3 L-L-
3 to 5 I
3 to 5 I
8.6.3 I
~-
~
r 29AOV-86C I
3 to 5 I
3 to 5 I
8.7.3 I
10.2 Level 2 Acceptance Criteria None Rev. NO. 23 Page 18 of 24
ST-1B L
~
~~
11.0 ACCEPTANCE VERIFICATION 11.1 SNO R e v i e w 11.1.1 11.1.2 11.1.3 NOTE :
11.1.4 11.1.5 11.1.6 11.1.7 Verify required data has been recorded and is within required tolerances.
Verify required initials and signatures have been entered.
IF Level 1 Acceptance Criteria OR Level 2 LLRT valve acceptance criteria was not met, THEN perform the following:
A. Sign off ST as unsatisfactory.
B. Immediately notify the CRS.
C. Initiate a DER.
D - If necessary, initiate a PID.
DER number d / A PID number A DER is required for instruments that exceed As Found tolerances for tracking purposes.
IF only Level 2 Acceptance Criteria was not met, THEN perform the following:
A. Sign of ST as satisfactory with corrective actions.
B. Initiate either a DER or a PID.
PID/DER number Identify test results:
(-)
Satisfactory L)
Satisfactory with corrective actions L)
Unsatisfactory e/Time
(
Record results in SNO log.
L-Rev. No. 23 Page 19 of 24
MSIV FAST CLOSURE TEST ( I S T )
ST-1B 11.2 Management SRO Review 11.2.1 Verify data is within required tolerances.
11.2.2 Verify data attachments, such as recorder printouts and calibration sheets are included as required.
11.2.3 Verify required initials and signatures have been entered.
11.2.4 Review test to determine if test results satisfy acceptance criteria:
(-)
Satisfactory
(-)
Satisfactory with corrective actions
(-1 Unsatisfactory 11.2.5 IF Level 1 acceptance criteria is not satisfied, THEN immediately notify Operations Manager or alternate. Record name of person notified.
Person Notified 11.2.6 Initiate required corrective and compensatory actions.
(-1 Not required
(-)
Required 11.2.7 Sign and record date and time.
Management SRO Rev. NO. 23 Date /T ime Page 20 of 24
ST-1B 11.3 IST Coordinator Review 11.3.1 Review test results.
11.3.2 Update records as required.
IST Coordinator Rev. No. 23 Date /Time Page 21 of 24
I MSIV FAST CLOSURE TEST ( I S T )
ST-1B 11.4 Remarks Page 22 of 24 Rev. No.
23
ST-1B MSIV FAST CLOSURE TEST ( I S T )
12. 0 ATTACHMENTS
- i.
TEST SIGNOFF LOG Rev. No.
23 Page 2 3 of 24
ST-1B ATTACHMENT 1 Page TEST SIGNOFF LOG PRINTED NAME INITIALS HOURS WORKED I
I I l
Total Man-Hours c 5 1 of 1 R e v. No.
23 Page 2 4 of 2 4
-4s
==- Entersy James A. FiePatrick Nuclear Power Plant Nuclear Northeast OPERATIONS TRAINING PROGRAMS SRO APPL. TO NEW JPM NUMBER TASK TITLE: AOP-28/43 Procedure Execution REV: 0 DATE:
JAF TASK NUMBER:
NRC K/A SYSTEM NUMBER:.31.2 JAF QUAL STANDARD NUMBER:
ESTIMATED SUBMITTED:
OPERATION Pr\\/lE\\*'-
\\ L V I L I..
v APPROVED:
CANDIDATE NAME:
S.S. NUMBER:
JPM Completion:
(
) Simulated
( X ) Performed Location:
(
) Plant
( X ) Simulator DATE PERFORMED:
PERFORMANCE EVALUATION:
( ) Satisfactory
( ) Unsatisfactory TIME TO COMPLETE: -
Minutes EVALUATOR:
S IG NATU RE/PR I NTE D CANDIDATE REVIEW:
SIGNATURE REVIEWED BY:
DOC. COMPLETE:
PROGRAM ADMINISTER Page 1 of 5
JCTb PEReORMANGt hcASUkt RECORD AND CHECKLIST L/ SRO NEW TASK TITLE: AOP-28/43 Procedure Execution APPL. TO JPM NUMBER Current Update: 5/21/03 By: RWD Date Int.
Outstanding Items:
Technical Review Additional Information Questions and Answers Validation Procedural Change Required None Comments:
Simulator validated 5/24/03. IC 133 Previous Revision Dates:
Page 2 of 5
JUb t.tKrUKfUhN~E MEAaUKk REQUIRED TASK INFORMATION t
SRO NEW TASK TITLE: AOP-28/43 Procedure Execution APPL. TO JPM NUMBER
- 1.
SAFETY CONSIDERATIONS A.
Ensure proper safety equipment and safety procedures are observed.
II.
REFERENCES A.
B.
AOP-28, Operation During Plant Fires, Rev. 12 AOP-43. Plant Shutdown From Outside The Control Room, Rev. 28 111.
TOOLS AND EQUIPMENT A.
None IV.
SET UP REQUIREMENTS A.
B.
C.
D.
MFI-FP02:Z69, Fire (smoke) alarm in North Cable Run Room inserted on trigger.
MFI-FP02:Z57, Fire (smoke) alarm in Relay room inserted on same trigger on 30 second TD Override on Cable Run Room High Temp Amber and C02 initiation Red lamps on same trigger with 10 second TD ANXXW. Randomly select multiple horseshoe annunciators to crywolf. Assign to the same trigger at varying time delays up to 2 minutes c-,
V.
EVALUATOR NOTES A.
If performing JPM in the plant, inform the candidate that the conditions of each step need only be properly identified and nat actually performed.
B.
The candidate should, at a minimum, identify the change in equipment status light indication when equipment operation is simulated.
VI.
TASK CONDITIONS A.
B.
C.
The set up above is modeling a North Cable Run Room large fire that has moved to the Relay Room in the vicinity of the Interposing Relay (annunciator} cabinets.
Fire Alarm, Suppression System Actuation, and verbal report confirm a large fire in the relay room.
Unexpected alarms confirm entry into AOP-28.
- - CRITICAL STEP L-Page 3 of 5
S/RO/NLO NEW TASK TITLE: AOP-28/43 Procedure Execution VII.
INITIATING CUE STEP STANDARD You are the Control Room Supervisor. Your panel operators are simulated. The plant is operating normally at 100% CTP. Respond accordingly to events unrelated to other candidates.
EVALUATION I COMMENT EVALUATOR Have simulator operator trigger fire alarm and after a short delay, call Control Room Supervisor to report a large fire in the Relay Room
~
Receive alarms Order fire brigade response per EAP-3 Reference AOP-28
- 1.
Candidate acknowledges and recognizes fire indication in north cable run room, relay room and suppression system actuation.
FVAl TOR When ordered, indicate that the Fire Brigade is respondina as directed Candidate obtains AOP-28.
SAT / UNSAT SAT / UNSAT SAT / UNSAT
- 2.
Enter AOP-28 Determine applicable AOP-28 Attachment Reference AOP-43 Enter AOP-43
- 3.
Candidate assesses that symptoms warrant AOP-28 entry at section C.
Candidate determines that AOP-28 exit and AOP-43 entry is required Candidate obtains AOP-43.
Candidate assesses that symptoms warrant AOP-43 entry at section C.
EVALUATOR Indicate to the candidate that he smells and sees smoke. The view of the 09-5 is hazy and worsening.
You may consider requesting additional random crywolf annunciators.
SAT / UNSAT SAT / UNSAT SAT / UNSAT SAT / UNSAT
- 4.
- 5.
- 6.
- 7.
I I
Page 4 of 5
i STEP STANDARD EVALUATION / COMMENT
- 8.
C.1.4 IF Control Room evacuation is required, OR a loss of shutdown capability from the Control Room occurs, THEN operators perform their assigned subsection, injection must occur within 30 minutes of initial SRV actuation:
Candidate determines that a control room evacuation is required and orders operators to perform their assigned subsections.
SAT / UNSAT EVALUATOR: Terminate the task at this Doint.
Page 5 of 5
James A. FitrPatrick Nuclear Power Plant SRO NEW TASK TITLE: TECHNICAL SPECIFICATION EVALUATION AND APPL. TO JPM NUMBER LCO TRACKING REV: 0 DATE: 5/23/03 NRC WA SYSTEM NUMBER: 7 1.17 7 914.0 JAF TASK NUMBER:
JAF QUAL STANDARD NUMBER:
ESTIMATED COMPLETION TIME: -l5--
Minutes SUBMITTED:
APPROVED:
OPERATION REVIEW:
/&
Y CANDIDATE NAME:
S.S. NUMBER:
JPM Completion:
( ) Simulated
( )Performed Location:
(
) Plant
( )Simulator DATE PERFORMED:
TIME TO COMPLETE: -
Minutes PERFORMANCE EVALUATION:
( ) Satisfactory
( ) Unsatisfactory EVALUATOR:
SIGNATUREIPRINTED CANDIDATE REVIEW:
SIGNATURE REVIEWED BY:
DOC. COMPLETE:
PROGRAM ADMINISTER L,
Page of 6
JOB PERFORMANCt MbSUKt RECORD AND CHECKLIST L.SRO NEW TASK TITLE: TECHNICAL SPECIFICATION EVALUATION AND LCO TRACKING APPL. TO JPM NUMBER Current Update: 5/23103 By: RWD Date lnt.
Outstanding Items:
Technical Review Additional Information Questions and Answers Validation Procedural Change Required None Comments:
Previous Revision Dates:
Page 2 of 6
JUB PERVWHMANbk MtASUflk REQUIRED TASK INFORMATION SRO NEW TASK TITLE: TECHNICAL SPECIFICATION EVALUATION AND APPL. TO JPM NUMBER LCO TRACKING
-v
- 1.
II.
111.
IV.
L-'
V.
VI.
SAFETY CONSIDERATIONS A.
Ensure proper safety equipment and safety procedures are observed.
REFERENCES A.
B.
Technical Specification 3.7.6, SR 3.7.6.1 and Bases ST-21 Q, Main Turbine Bypass Valve Cycle Test, Rev. 0 C.
AP-19.01. SURVEILLANCE TESTING PROGRAM TOOLS AND EQUIPMENT A.
None SET UP REQUIREMENTS A.
Best if conducted in \\,,e Contro Room or the simulator.
B.
If performed in alternative locations, normal controlled references and prints may need to be available.
EVALUATOR NOTES A.
B.
TASK CONDITIONS A.
B.
ST-21Q is in progress.
C.
D.
A plant startup is in progress, making preparations to enter Mode 2.
SNO reports that BPV-3 will not open and therefore will not meet the level 1 acceptance criteria. BPV-1 and 2 responded properly Candidate evaluates Tech Spec impact of the failure.
' - CRITICAL STEP L-,
Page 3 of 6
S/RO/NLO NEW TASK TITLELTASK TITLE: TECHNICAL SPECIFICATION EVALUATION STANDARD Candidate will determine that the BPV-3 is inoperable EVALUATOR If requested, provide blank copy of ST-21Q Candidate determines that BPV-3 has failed SR-3.7.6.1 and LCO 3.7.6 is affected.
Candidate determines that Applicability of LCO is not met and LCO is therefore not applicable.
Candidate also determines that plant operation is limited to ~ 2 5 %
EVALUATC)R If the candidate initiates any of the below, report that they are in progress:
6 Management Notifications Problem Identification (PID) process Corrective Action (CR) Process VII.
INITIATING CUE EVALUATION I COMMENT '
SAT / UNSAT SAT / UNSAT SAT / UNSAT You are the SMICRS. A plant startup completing a refuel outage is in progress. Preparations are being made to enter Mode 2. ST-21QI MAIN TURBINE BYPASS VALVE CYCLE TEST, is in progress. The SNO reports that Bypass Valve Number 3 will not open and will therefore fail the level 1 acceptance criteria. Bypass Valves 1 and 2 responded properly.
EVALUATOR Hand candidate Attachment 1, Initiating Cue Interactive discussion may be required to facilitate this evaluation I
- 2.
- 3.
- 4.
STEP Assess the report Determine Technical Specification amlicabilitv Declare Bypass System inoperable Page 4 of 6
.TASK TITI
- 5.
- 6.
EVALUATOR: Terminate the task at this point.
STEP STANDARD Initiate LCO tracking process EVALUATOR Candidate prompting may be required.
EVALUATION / COMMENT SAT / UNSAT I and2 I
Complete AP-12.08, Attachment 1 and 2 of this JPM contains AP-I 2.08 and 2 kev entries for this condition Candidate obtains AP-12.08 or LCO tracking binder and determines that LCO trackina is rewired FVAl UATOR SAT / UNSAT Provide candidate with blank AP-12.08 Attachment 1 Page 5 of 6
ATTACHMENT I L-You are the SMCRS. A plant startup completing a refuel outage is in progress.
Preparations are being made to enter Mode 2. ST-ZIQ, MAIN TURBINE BYPASS VALVE CYCLE TEST, is in progress. The SNO reports that Bypass Valve Number 3 will not open and will therefore fail the level 1 acceptance criteria. Bypass Valves 1 and 2 responded properly.
Page 6 of 6
i 1
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I This IS NOT a Quality Record L*
1 AP-12-08 I Rey:.
No. 3 LCO TRACKING AND SAFE??' FUNCTION DET&R.M,INATION P R O G M ATTACHMENT 2 Page 41 of 4 9
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__ CONDITIOX
'- I R e q u i r e d by:
D a t e :
I' T i m e :
R e q u i r e d by:
D a t e :
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T i m e :
R e q u i r e d by:
Date:-:
T i m e :
23 IF OTHER THAK O?
Com;lezec:
Daze:
T i m e :
IElZlals :
Date:
A i m e :
L21zlals :
RZQL'IXZZ' TC COMPLETE
==-==I I
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I This Is a Quality Record
'v ATTACHMENT 1 Page 37 of 49 1 A?-;2.08 I Re;..
N o. 3 L C O TXACXING AND SAFETY FUNCTION DETERMINATIOX P R O G W A
daze i L-1 A P - i ?. O e K
O TRACKING AND SAFETY FUNCTION DETERMINATION P R O G M ATTACHMENT 1 Re17. No. 3
?age 2 of 49 I
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This a Quality Record
.e A ? - 1 2. 0 8 LCC TTACKING AN3 SAET?' FUNCTION DETERYINATZON P R O G W.
ATTACHMEKT 1 Rex-. No. 3 Page 3c of 49 I
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I
c This Is a Quality Record l-.-
1 AP-12.08 LCO TRACKING AND SAFETY FUNCTION DETERMINATION P R O G N ATTACHMENT 1 R e v. No. 3 Page 40 of 45,
EAL DECLARATION JPM'S FILED WITH APPROPRIATE SCENARIOS v
twu James A. FitzPatrick Nuclear Power Plant Nuclear Northeast b
OPERATIONS TRAINING PROGRAMS JOB PERFORMANCE MEASURE 330 6 N d S/RO NEW TASK TITLE: PERFORM CONTROL ROOM ACTIONS FOR STQOC APPL. TO JPM NUMBER REV: 0 DATE: 6/5/03 NRC WA SYSTEM NUMBER: 24.21 JAF TASK NUMBER:
JAF QUAL STANDARD NUMBER:
ESTIMATED COMPLETION TIME: Ifj Minutes SUBMITTED:
OPERATION REVIEW:
APPROVED:
CANDIDATE NAME:
S.S. NUMBER:
JPM Completion:
( ) Simulated
( X ) Performed i--
Location:
( ) Plant
( X ) Simulator DATE PERFORMED:
PERFORMANCE EVALUATION:
( ) Satisfactory
( ) Unsatisfactory TIME TO COMPLETE: ___ Minutes EVALUATOR:
SIGNATURE/PRINTED CAN DlDATE REVIEW:
SIGNATURE REVIEWED BY:
DOC. COMPLETE:
PROGRAM ADMINISTER Page I of 8
-SlRO NEW TASK TITLE: PERFORM CONTROL ROOM ACTIONS FOR ST-4OC APPL. TO JPM NUMBER Current Update: 6/5/03 By: RWD Date Int.
Outstanding Items:
Technical Review Additional Information Questions and Answers Validation Procedural Change Required None Comments:
Previous Revision Dates:
None Page 2 of 8
---.S/RO NEW APPL. TO JPM NUMBER TASK TITLE: PERFORM CONTROL ROOM ACTIONS FOR ST4OC
- 1.
II.
111.
IV.
- u-V.
VI.
SAFETY CONSIDERAT DNS A.
Ensure proper safety equipment and safety procedures are observed.
REFERENCES A.
ST40C, COMPUTER OUT OF SERVICE SURVEILLANCE, Rev. 16 TOOLS AND EQUIPMENT A.
Simulator Telephone to Instructor Console (Optional)
SET UP REQUIREMENTS A.
B.
Reset the Simualtor to any at power IC with the Generator synced to the grid.
Insert Override Pen 2, 06PRER-98 NR RX PRESS TURB STM FLOW, to fail downscale.
EVALUATOR NOTES A.
If performing JPM in the plant, inform the candidate that the conditions of each step need only be properly identified and mt actually performed.
The candidate should, at a minimum, identify the change in equipment status light indication when equipment operation is simulated.
B.
TASK CONDITIONS A.
EPIC has been lost.
B.
The Shift Manager has directed that ST-4OC, COMPUTER OUT OF SERVICE SURVEILLANCE, section 8.4.2, TREND RECORDER CHECK, be performed.
- - CRITICAL STEP Page3 of 8
S/RO/NLO NEW TASK TITLE: PERFORM CONTROL ROOM ACTIONS FOR ST-40C VII.
INITIATING CUE EPIC has been lost. The Shift Manager has directed that ST40C, COMPUTER OUT OF SERVICE SURVEILLANCE, section 8.4, TREND RECORDER CHECK, be performed.
EVALUATOR Evaluation of candidate will be based on verifying that the candidate clearly checks all of the listed instrumentation and the critical step will be to identify the faulted instrument, 06PUFR-98 NR RX PRESS TURB STM FLOW, has failed.
~-
STEP Candidate obtains procedure ST-40CI COMPUTER OUT OF SERVICE SURVEILLANCE
- 1.
- 2.
- 3.
-~
STANDARD EVALUATION / COMMENT Candidate selects ST40C, COMPUTER OUT OF SERVICE SURVEILLANCE.
Candidate identifies Section 8.4, TREND RECORDER CHECK SAT / UNSAT EVALllATnR Upon Section selection, hand candidate a partially performed copy of ST40C, COMPUTER OUT OF SERVICE SURVEILLANCE NIA following instruments:
Performs step 8.4.2-verifying each of the Candidate reviews procedure 8.4 Trend Recorder Check 8.4.2 Verify trend recorders listed below are trending data and the parameter recorded is indicating the expected value.
- 4. ' 7RR-53 STACK RANGE RAD CANDlDATE Initials for 17RR-53 STACK HIGH RANGE MON RAD MON EVALUATOR monitor candidate to ensure he/she verifies indicated value is:
SAT / UNSAT Page 4 of 8
SIROlNLO NEW 17RR-455 RX BLDG VENT MON (BELOW REFUEL FLOOR)
- 7.
ASK TITLE: PERFORM CONTROL ROOM ACTIONS FOR ST-QOC I
I I
FXALUATOR monitor candidate to ensure he/she verifies indicated value is:
C, & U U E Initials for 17RR-455 RX BLDG VENT MON (BELOW REFUEL FLOOR)
EVAL.LIATOR monitor candidate to ensure he/she verifies indicated value is:
SAT I UNSAT EVALUATOR monitor candidate to ensure he/she verifies indicated value is:
16-ITR-131A TORUS TEMP A
- 0.
27PR-I 15A1 PC PRESS
- 9.
27PR-115A2 PC PRESS I O.
23LR-203A PC LVL
- 11.
17RR-463 RADW HI RANGE VENT CANDlDATE Initials for 17RR-463 RADW HI RANGE 6'
1 MON VENT MON SAT I UNSAT CANDlOATE Initials for 16-ITR-131A TORUS TEMP A FVAl jJAIf)R monitor candidate to ensure heIshe verifies indicated value is:
CLLNDlDLIiTE initials for 27PR-I 15A1 PC PRESS FVAl LIAIQR monitor candidate to ensure heishe verifies indicated value is:
SAT / UNSAT SAT / UNSAT Initials for 27PR-115A2 PC PRESS F
monitor candidate to ensure heIshe verifies indicated value is:
CANDlDATE Initials for 23LR-203A PC LVL EVALUATOR monitor candidate to ensure heIshe verifies indicated value is:
SAT I UNSAT SAT I UNSAT Page 5 of 8
(
SIROINLO NEW 3 FOR ST40C STANDARD CANDlDATE Initials for 23LR-202A TORUS LVL EVALUATOR monitor candidate to ensure he/she verifies indicated value is:
CANDlDATE Initials for 06PR-61A RX VESSEL PRESS E V A b l monitor candidate to ensure he/she verifies indicated value is:
-ATE, Initials for 27PR-115B2 PC PRESS E
U L
monitor candidate to ensure he/she verifies indicated value is:
CANDlDATE Initials for 27PR-I 1581 PC PRESS EVALUATOR monitor candidate to ensure he/she verifies indicated value is:
CANDlDATE Initials for 23LR-203B PC LVL F3LALLIAIC)R monitor candidate to ensure he/she verifies indicated value is:
C A N D l D R Initials for 23LR-2028 TORUS LVL f3AUKEB monitor candidate to ensure heishe verifies indicated value is:
CANDlDATE Initials for 06PR-61 B RX VESSEL PRESS FVAI_IIATC)R monitor candidate to ensure he/she verifies indicated value is:
4SK TITLE: PERFORM CONTROL ROOM ACTIC STEP 23LR-202A TORUS LVL
- 12.
EVALUATION I COMMENT SAT I UNSAT SAT / UNSAT SAT / UNSAT SAT / UNSAT SAT I UNSAT SAT / UNSAT SAT / UNSAT 06PR-61A RX VESSEL PRESS
- 13.
~
~~~
- 14.
27PR-115B2 PC PRESS 27PR-115Bl PC PRESS
- 15.
23LR-203B PC LVL
- 16.
23LR-2026 TORUS LVL
- 17.
06PR-61 B RX VESSEL PRESS
- 18.
Page 6 of 8
r S/RO/NLO NEW ASK TITLE: PERFORM CONTROL ROOM ACTIONS STEP 16-1 TR-108 DW TEMP A
- 19.
IOFR-143 RHR FLOW
- 20.
02-3LR-98 RX WTR LVL FUEL ZONE
- 21.
16-ITR-131B TORUS TEMP B
- 22.
16-1 TR-107 DW TEMP B
- 23.
FOR ST-40C STANDARD CANDlDATE Initials for 16-1 TR-108 DW TEMP A EVALUL\\TOR monitor candidate to ensure helshe verifies indicated value is:
CANnlDATE Initials for 1 OFR-I43 RHR FLOW FVAl IJATOB monitor candidate to ensure he/she verifies indicated value is:
CANRKlATE Initials for 02-3LR-98 RX WTR LVL FUEL ZONE FVAl IlATOR monitor candidate to ensure he/she verifies indicated value is:
CANDlDATE Initials for 16-ITR-131 B TORUS TEMP 6 EVI1I_UATOR monitor candidate to ensure helshe verifies indicated value is:
lXWRAIE Initials for 16-1 TR-107 DW TEMP B F3UMIQ.R monitor candidate to ensure he/she verifies indicated value is:
EVALUATION I COMMENT SAT I UNSAT 16-1 DPR-200 DW PRESS,TORUS PRESS, DW TO TORUS DIFF PRESS CANDlDATE Initials for 16-1 DPR-200 DW PRESS,TORUS PRESS, DW TO TORUS DlFF PRESS EVALUATOR monitor candidate to ensure helshe verifies indicated value is:
- 24.
SAT / UNSAT SAT I UNSAT SAT l UNSAT SAT l UNSAT SAT / UNSAT Page 7 of 8
SIROINLO NEW STEP 02TR-165 RWR LOOP INLET TEMP
- 25.
ASK TITLE: PERFORM CONTROL ROOM ACTIONS FOR ST-40C I
I I
STANDARD EVALUATION / COMMENT i
CANOlDATE, Initials for 02TR-165 RWR LOOP INLET TEMP SAT / UNSAT 1
F V A l UATOR monitor candidate to ensure he/she verifies indicated value is:
- 26.
- 27.
- 2a.
Note-The D6LRIPR-97 WR RX PRESS RX LVL 02-3LR-85B RX WTR LVL 06PRIFR-98 NR RX PRESS TURB STM FLOW dlowing Instruments are located on Panel-09-5 CMURAIE Initials for 06LRIPR-97 WR RX PRESS RX LVL F V A l IIATQR monitor candidate to ensure he/she verifies indicated value is:
CANDIC]ATE Initials for 02-3LR-85B RX WTR LVL F V A l UATOR monitor candidate to ensure he/she verifies indicated value is:
CANDlOATE Determines that 06PRIFR-98 NR RX PRESS TURB STM FLOW has failed downscale and reports to Supervision.
EVAL.IIATOR monitor candidate to ensure he/she verifies indicated value is:
Role Play Acting as Supervisor-Acknowledge report and direct candidate to terminate task
~-
SAT I UNSAT SAT / UNSAT CRITICAL TASK SAT / UNSAT
I EYALUXB: Terminate the task at this Doint.
Page 8 of 8
ENTERGY NUCLEAR OPERATIONS, INC.
SURVEILLANCE TEST PROCEDURE JAMES A. FITZPATRICK NUCLEAR POWER PLANT COMPUTER om OF SHWZCE 8vRvEIwwLwcE ST-4OC RMISIOW 16 APPROVED BY:
- SPONS$BLE P~OCEDURE OW&R DATE 2(/
(
EFFECTIVE DATE :
FIRST ISSUE 0 FULL REVISION 0 LIMITED REVISION n?ERENCE USE TSR TECHNICAL
COMPUTER OUT OF SERVICE SURVEILLANCE ST-40C REVISION
SUMMARY
SHEET REV. NO.
CHANGE AND REASON FOR CHANGE 16 Added Attachments 3 and 6, l i s t e d a key i n Subsection 5. 2,
added Subsection 8. 3, added Step 8. 9. 4, added Step 10.1.4 and revised Subsection 1. 2 t o provide method f o r calculating average drywell temperature on a l o s s of p l a n t computer.
CA-02-2922-1 L
15 Deleted t h e requirement t o record Calibration Due Dates i n Sections 4 and 5 per ODSO-31.
Revised Step 6. 2. 5 t o be consistent with Surveillance T e s t format.
The electric lift f e a t u r e of SRV's is no longer bypassed i n ST-40C.
(ACT-01 -60461) (PCR #1 dated 8/25/01) :
Deleted OP-68 from references Added b u l l e t t o Step 8. 1. 1 as s h i f t discussion i t e m.
Revised and r e t i t l e d Subsection 8. 7, avoiding r e s t r i c t i v e and unnecessary LCO.
Revised Step 8. 8. 3 t o monitor v i c e restore.
Deleted Step 9.1.2 Added Step 8. 2. 1 t o ensure compliance with t h e SPDES permit.
Clarified Step 9.2.1 calculations are performed on Attachment 2.
Added "Average" before "screenwell" i n Step 10.1.1 t o reflect t h e name as indicated i n Step 8. 2. 4 and Attachment 2.
Added "Average" before "plant" i n Step 10.1.2 t o reflect t h e name as indicated i n Step 8. 2. 5 and Attachment 2.
Corrected t i t l e of last t a b l e column on Attachment 4 t o be consistent with action taken.
Revised Section 1.2 t o include Improved Technical Specification references.
The following changes have been made t o support t h i s
'L.'
Rev. No.
16 Page 2 of 40
A COMPUTER OUT OF SERVICE SURVEILLANCE ST-40C TABLE OF CONTENTS SECT1 ON 1.0 REQUIREMENTS 2.0 PURPOSE........................
3.0 REFERENCES
4.0 PREREQUISITES.....................
5.0 TEST EQUIPMENT, SPECIAL TOOLS AND MATERIALS......
6.0 PRECAUTIONS AND LIMITATIONS..............
7.0 GENERAL TEST METHODS 8.0 PROCEDURE.......................
8.1 Required Notifications and Briefings 8.2 Circulating Water Temperature Check..........
8.3 Drywell Temperature Check...............
8.4 Trend Recorder Check 8.5 Balance o f Plant Check 8.6 Rod Worth Minimizer Inoperable Check 8.7 Core Thermal Power Evaluation.............
8.8 Additional Monitoring of SRV Electric Lift Feature 8.9 Restoration......................
9.0 RETURN TO NORMAL 10.0 ACCEPTANCE CRITERIA..................
11.0 ACCEPTANCE VERIFICATION................
12.0 ATTACHMENTS......................
~.--/
1. TEST SIGNOFF LOG 2. INTAKE. DISCHARGE. AND INTAKE-DISCHARGE DIFFERENTIAL TEMPERATURE CALCULATION PAGE 4
4 5
6 7
8 10 11 1 1 12 14 16 19 19 19 20 21 22 23 24 27 28 29 3. DRYWELL TEMPERATURE CALCULATION..........
33 4. RESISTANCE VS TEMPERATURE TABLE..........
34 5. CIRC WATER RTD LIFTED LEAD CONTROL FORM......
36 6. DRYWELL RTD LIFTED LEAD CONTROL FORM 38 Rev. No.
16 Page 3 of 40 L
c 1.o 1. 1 1.2 1. 3 1.4 2.o SR OUT OF SERVICE SURVEILLANCE ST74OC EQUIREMENTS requency 3ch shift when the Emergency Plant Information Computer EPIC) is inoperable echnical Specifications
.2.1 Surveillance Requirements SR 3. 6. 1. 5. 1
.2.2 Limiting Conditions for Operation LCO 3. 3. 2. 1 and Table 3. 3. 2. 1 - 1 Function 2 LCO 3. 6. 1. 5 ther
. 3. 1 Permit Requirements CP-04.03, State Pollutant Discharge Elimination System Permit ommi tments one URPOSE o provide a checklist to ensure plant parameters which are ormally monitored, displayed, and recorded by the Emergency lant Information Computer (EPIC), are being monitored, isplayed, and recorded by the following methods:
Trend recorders Auxiliary operator plant tours and operating logs Determining screenwell intake temperature, plant discharge temperature, and intake-discharge differential temperature Rev. No.
16 Page 4 of 40
COMPUTER OUT OF SERVICE SURVEILLANCE ST-4OC 3. 0 REFERENCES 3.1 Performance References 3. 1. 1 CP-04.03, S t a t e P o l l u t a n t Discharge Elimination System Permit.
3. 1. 2 OP-64, Rod Worth Minimizer 3. 1. 3 ST-5E, Core Performance Daily Surveillance 3.1.4 ODSO-17, Auxiliary Operator P l a n t Tour and Operating Logs 3. 1. 5 EP-1, EOP Entry and Use 3. 1. 6 AOP-61, Screenwell Intake Temperature High 3. 2 Developmental References 3. 2. 1 Modification F1-88-050, GEPAC Removal, IP-1, Ap endix I Curve No. 5 Resistance VS Temperature Ta E le 100 Platinum RTD 3. 2. 2 JAF-SE-96-048, Revision 1, Revision t o FSAR t o Raise Maximum Allowable Lake Temperature From 82°F to 85°F 3. 2. 3 3. 2. 4 3. 2. 5 3. 2. 6 3. 2. 7 3.2.8 3. 2. 9 3.2.10 3.2.11 3.2.12 3.2.13 3.2.14 3.2.15 3.2.16 M1-97-070, SRV Electric L i f t Feature / ATWS Level 2 Setpoint Change FE-36AA FE-36AB FE-36AC FE-36AD FE-81C FE-81G FE-9OF FE-SOH FM-49A SE - 9ABE SE - 9ABV SE-9ACG SE-9ADC Rev. No.
16 Page 5 of 40
COMPUTER OUT OF SERVICE SURVEILLANCE ST-40C NOTE:
Sections 4 and 5 may be performed in any order o r concurrently.
I n i t 4.0 PREREQUISITES 4. 1 4.2 s!
SM has granted permission t o perform t h i s test.
Revision Number of t h i s Workin revision number l i s t e d i n the Easter Copy of t h e Index of Operations Surveillance Test Procedures.
T e s t personnel have read t h i s procedure and are Copy is the same as the 4. 3 thoroughly familiar with its contents.
/-
4.4 S t a r t of test recorded.
/ c hl'1hkJ ccjc Bate/Time n
4.5 S t a r t of test recorded i n SNO Log.
cl/
4. 6 I&C Department notified t h a t I&C assistance is required. -!?
4. 7 Required M&TE verified t o be within calibration and its identification number recorded i n Subsection 5. 1.
Rev. No.
16 L
Page 6 of 40
COMPUTER OUT OF SERVICE SURVEILLANCE ST-40C 5. O 5.1 5.2 5. 3 TEST EQUIPMENT, SPECIAL TOOLS AND MATERIALS Test Equipment 5.1.1 RTD Readout and Simulator Model No. / 5 I&C No. dG ch 2 5.1.2 Digital Multimeter 17R 14 i I&C No.
Special Tools Key #Orange-520 for Foxboro 09-24 & 09-25 panels Materials Tags for marking disconnected leads Rev. No.
16 Page 7 of 40 I
L-COMPUTER OUT OF SERVICE SURVEILLANCE ST-40C 6.0 PRECAUTIONS AND LIMITATIONS 6. 1 Precautions 6. 1. 1 Disconnected electrical leads s h a l l be i n s u l a t e d using small sections o f electrical insulation sleeving taped t o t h e wire insulation.
Non-shrunk heat shrink tubing may also be used.
Disconnected leads should not be insulated with electrical t a p e, as t h e adhesive can remain on t h e conductor when removed.
NOTE :
An acceptable method f o r insulating adjacent terminals is electrical tape placed over t h e top of t h e terminal board.
6. 1. 2 Before connecting o r disconnecting electrical jumpers o r leads, personnel s h a l l ensure adjacent terminals, exposed metal, t o o l s, and test equipment are insulated as necessary t o prevent accidental shorting o r grounding.
6. 2 Limitations 6.2.1 6.2.2 T e s t personnel s h a l l p r i n t name, sign i n i t i a l s, and T e s t personnel s h a l l immediately notify t h e CRS o f any failure t o meet acceptance criteria.
enter date on Attachment 1 before performing Section 8 o f t h i s t e s t.
6. 2. 3 When test personnel complete t h e i r assigned portion of t h i s test, they s h a l l enter dose received and hours worked on Attachment 1.
Rev. No.
16 Page 8 of 40
COMPUTER OUT OF SERVICE SURVEILLANCE ST-40C L-6. 2. 4 Once t h i s test has been s t a r t e d, any additional test personnel s h a l l read t h i s procedure and become thoroughly familiar with its contents before performing any portion of t h i s test.
6. 2. 5 Multiple workin copies of t h i s test may be used provided t h e f o !?
lowing requirements are s a t i s f i e d :
NOTE: The work site is defined as t h e location where work is controlled. The location of t h e work site is a t t h e discretion of t h e SNO.
A working copy of t h i s test s h a l l be retained a t t h e work s i t e.
A.
The work s i t e working co y s h a l l be t h e l e g a l record f o r documenting t is t e s t.
Data from a l l s t e p s performed away from t h e work site, including signatures, i n i t i a l s,
and recorded values, is transcribed i n t o t h e work site working copy following completion o f t h e test.
K B.
C.
Rev. No.
16 Page of 40
COMPUTER OUT OF SERVICE SURVEILLANCE ST-40C 7.0 GENERAL TEST METHODS 7. 1 This test consists of six subsections which provide increased monitoring o f parameters normally monitored by EPIC.
Subsections 8. 2 through 8.8 may be performed i n any order necessary t o facilitate plant o erations. Subsection 8. 2 is 7. 2 performed once each hour while E PIC is out of service.
Rev. No.
16 Page 10 of 40
-. -I--
..--I
-. I ST-40C 8.0 PROCEDURE teps 8. 1. 1 through 8. 1. 3 may be performed n any order or concurrently.
as on plant operations.
A s a-minimum,-
the following :
Monitoring alternate indications l i s t e d i n EP-1 on a frequent and continuous basis.
Expedient investigation and reporting of a l l annunciators and alarms on panels, including panels located outside of the Control Room.
Obtaining circulating water temperatures on an hourly basis t o comply with the SPDES permit.
Core thermal data, including thermal l i m i t data t h a t mav not be available.
Making detailed building rounds on an increased frequency.
Reporting off -normal observations upon detection.
Monitoring SRV electric lift alternate indication on a frequent basis.
8. 1. 2 Ensure all on s h i f t licensed reactor operators and senior reactor operators review EP-1.
8. 1. 3 Notify a computer specialist.
Rev. No.
16 Page 1 1 of 40
-~
COMPUTER OUT OF SERVICE SURVEILLANCE ST-40C 8. 2 Circulating Water Temperature Check I n i t NOTE 1 :
NOTE 2:
8.2.1 8.2.2 8.2.3 NOTE 1 :
NOTE 2:
8. 2. 4 8. 2. 5 may be photocopied as necessary f o r hourly c i r c u l a t i n g water temperature checks.
Leads t h a t were disconnected t o determine c i r c u l a t i n g water temperatures do not require re-connection u n t i l t h e computer is restored and t h e f i n a l set of hourly temperature checks is performed.
WHILE EPIC is inoperable, perform Subsection 8.2 hourly t o comply with SPDES permit.
I F leads have not been disconnected, TEEN disconnect leads l i s t e d on Attachment 5 as follows.
Document performance on :
A.
Ensure lead is labeled.
B.
C.
Disconnect lead.
Hang tag on lead s t a t i n g lead is disconnected per ST-40C.
Direct I&C t o determine and record temperatures for t h e EPIC computer points on Attachment 2 once each hour using an RTD Readout & Simulator or Multimeter.
EPIC-A-1503 corresponds t o 36RTD-105B2 and EPIC-A-1504 corresponds t o 36RTD-105A2 Screenwell I n l e t Temperatures on Attachment 2 AOP-61 contains current entry conditions based on screenwell intake temperature.
Determine average screenwell intake temperature by completing calculation on.
Determine average c i r c u l a t i n water i n l e t.
temperature by completing ca f culation on NR L
Rev. No.
16 Page 12 of 40
1 COMPUTER OUT OF SERVICE SURVEILLANCE ST-40C Init 8.2.6 Determine average plant dischar e water.
temperature by completing calcu K ation on 8.2.7 Determine intake-discharge differential temperature by completing calculation on.
Rev. No. 16 Page 13 of 40
COMPUTER OUT OF SERVICE SURVEILLANCE STy4OC 8. 3 Drywell Temperature Check NOTE 1 : may be photocopied as necessary f o r daily drywell temperature checks.
Leads t h a t were disconnected t o determine drywell temperatures do not require re-connection u n t i l t h e computer is restored and t h e f i n a l set o f d a i l y temperature checks is performed.
NOTE 2:
8. 3. 1 8. 3. 2 8. 3. 3 WHILE EPIC is inoperable, perform Subsection 8. 3 every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> t o comply SR 3. 6. 1. 5. 1.
IF leads have not been disconnected, TEEN disconnect leads l i s t e d on Attachment 6 as follows.
Document performance on :
A.
Ensure lead is labeled.
B.
C.
Disconnect lead.
Hang t a g on lead s t a t i n g lead is disconnected per ST-40C.
Direct I&C t o perform t h e following once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> using an RTD Readout &
Simulator o r Multimeter and Attachment 3.
A.
I F a legitimate reading can be obtained from one RTD i n an associated DRYWELL AREA, B.
I n i t NR THEN lace a checkmark on Attachment 3 indicated temperature i n t h e READING column.
I F neither RTD for an associated DRYWELL AREA is providing a legitimate readin,
f o r t R e RTD monitored and record t h e TEEN erform t h e F ollowing on Attac R ment 3 :
1. Record "none" f o r READING 2. Line out t h e associated WEIGHTING FACTOR 3. Record "0" under CORRECTED VALUE Rev. No.
16 Page 14 o f 40
COMPUTER OUT OF SERVICE SURVEILLANCE ST-40C 8. 3. 4 Determine avera e drywell temperature by :
A.
performing t h e F ollowing using Multiply the recorded READING by t h e WEIGHTING FACTOR and record t h e r e s u l t under CORRECTED VALUE.
I F t h e READING f o r any DRYWELL AREA was recorded as "none" on,
THEN perform t h e following:
1. Record t h e sum of a l l t h e used B.
WEIGHTING FACTORS i n the SUM OF USED WEIGHTING FACTORS block.
2. Record t h e sum of a l l the CORRECTED VALUES i n the SUM OF CORRECTED VALUES block.
C.
IF no DRYWELL AREAS had a READING recorded as "none",
THEN perform t h e following:
1. Record "1" i n t h e SUM OF USED WEIGHTING FACTORS block.
2. Record t h e sum of a l l t h e CORRECTED VALUES i n the SUM OF CORRECTED VALUES block.
D.
Determine average drywell temperature by dividing t h e SUM OF CORRECTED VALUES by t h e SUM OF USED WEIGHTING FACTORS and record t h e r e s u l t as t h e AVERAGE DRYWELL TEMPERATURE on.
Rev. No.
16 Page 15 of 40
COMPUTE 8. 4 Tr 8.
- 8.
OUT OF SERVICE SURVEILLANCE ST-40C nd Recorder Check I n i t
.1 I F recorder is not required t o be operational for current plant conditions AND trend recorder is not operating, TEEN mark recorder "NA".
NR
. 2 Verify trend recorders l i s t e d below are trending data and t h e parameter recorded is indicating t h e expected value.
ANEL 09-2 17RR-53 STACK HIGH RANGE RAD MON 17RR-434 TURB BLDG H I RANGE VENT MON 17RR-463 RADW H I RANGE VENT MON 17RR-455 RX BLDG VENT MON (BELOW REFUEL FLOOR)
ANEL 09-3 16-1TR-131A 27PR-115Al 27PR-115A2 23LR-203A 2 3LR - 202A 06PR-6 1 A 27PR-115B2 27PR-115B1 2 3LR - 203B 23LR-202B 06PR - 6 1 B 16-1TR-108 10FR-143 02-3LR-98 16-1TR-131B 16-1TR-107 (Continued on next page)
Rev. No.
16 TORUS TEMP A PC PRESS PC PRESS PC LVL TORUS LVL RX VESSEL PRESS PC PRESS PC PRESS PC LVL TORUS LVL RX VESSEL PRESS DW TEMP A RHR FLOW RX WTR LVL FUEL ZONE TORUS TEMP B DW TEMP B Page 16 of 40
COMPUTE!
OUT OF SERVICE SURVEILLANCE ST - 40C I
I I
/ I 68TR-101 DW COOL AND DW TEMP
(->
68TR-103 DW COOL AND DW TORUS TEMP
(-1 I !
27R-101 TORUS LEVEL
(-1 Init 16-1DPR-200 DW PRESS,TORUS PRESS, 02TR-165 RWR LOOP INLET TEMP DW TO TORUS DIFF PRESS
(-1 06LR/PR-97 WR RX PRESS RX LVL
(-1 02-3LR-85B Rx WTR LVL
(-1 06PR/FR-98 NR RX PRESS TURB STM FLOW (3
SRM COUNTS
(-1 07PR-46A,B, APRM/IRM/RBM C, and D
(-1 27PCR-101A TORUS HYDROGEN/OXYGEN CONCENTRATION
(-1 CONCENTRATION
(-1 27PCR-101B DRYWELL HYDROGEN/OXYGEN t
68TR-102 DW COOL AND DW TORUS TEMP (3
111 27R-102 TORUS LEVEL
(-1 (Continued on next page)
Rev. No. 16 Page 17 of 40
8.4.2 (Cont)
PANEL 67HV-1 17RR-433 TI3 VENT MON REC PANEL 66HV-3A 17RR-456 REFUEL FLOOR EXH MON REC PANEL 69HV-12 17RR-458 RADWASTE VENT MON REC COMPUTER OUT OF SERVICE SURVEILLANCE ST-40C Rev. No.
16 Init Page 18 of 40
alance of Plant Check I n i t TE:
Only one set of Auxiliary 0 erator Plant Tour Logs is re uired if EP K C is out of service for LES 3 THAN 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
omplete the following Auxiliary Operator Plant Tour ogs per ODSO-17 at least every 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />s:
Reactor Building Tour Log Turbine Building Tour Log Radwaste Building Tour Log ubsection 8. 6 may be marked "NA" if not applicable.
Worth Minimizer Inoperable Check the EPIC failure caused the Rod Worth Minimizer the Rod Worth Minimizer is required, become inoperable, N comply with Section E of OP-64.
e Thermal Power Evaluation F all of the following conditions e x i s t :
Core thermal power data is not available from Monicore, AND Reactor power is GREATER THAN OR EQUAL TO 25%,
AND It is anticipated t h a t Monicore w i l l not be available for next scheduled ST-5E, THEN notify Reactor Analyst Group.
Rev. No. 16 L - 2 Page 19 of 40
COMPUTER OUT OF SERVICE SURVEILLANCE S T - 4 0 C 8.8 Additional Monitoring o f SRV Electric L i f t Feature NOTE :
Bypassing t h e SRV electric l i f t feature as a r e s u l t o f t h e l o s s o f E P I C is not required, based on regulatory requirements.
A heightened operator awareness of t h e s t a t u s of SRV electric l i f t is desired and obtained by more frequent monitoring of relay room panel indications.
Monitor indications which rovide "precursor" information of f e a t u r e, such as, but not limited t o :
local supervisory l i g h t s (which detect i n i t i a t i o n ressure indications (showin if one o f t h e four pressure a problem o r potential pro E l e m w i t h t h e SRV electric lift signals)
!oops or if a transmitter ha 8 failed) bypass switch position and corresponding l i g h t indications (if any SRV electric lift feature is bypassed)
Rev. No.
16 Page 20 of 40
~ _ _ _ _ _ _
COMPUTER OUT OF SERVICE SURVEILLANCE ST-40C L-8.9 Restoration WEEN computer has been restored, perform t h e following:
c-8. 9. 1 8. 9. 2 8.9.3 8.9.4 8.9.5 Rev. No.
16 Obtain f i n a l set o f c i r c u l a t i n g water temperature readings.
Obtain f i n a l set of drywell temperature readings.
Reconnect leads l i s t e d on Attachment 5 by performing t h e following.
Document performance on Attachment 5:
A.
Reconnect lead.
B.
Remove t a g s t a t i n g lead l i f t e d per ST-40C.
Reconnect leads l i s t e d on Attachment 6 by performing t h e following.
Document performance on Attachment 6 :
A.
Reconnect lead.
B.
Remove tag stating lead l i f t e d per ST-40C.
I n i t WHEN directed b SM, secure from additional monitoring of S !i V electric lift feature.
Page 21 of 40
COMPUTER OUT OF SERVICE SURVEILLANCE ST-40C I n i t L
9.0 RETURN TO NORMAL 9.1 System Restoration 9. 1. 1 Leads l i f t e d per Attachment 5 have been reconnected.
9. 1. 2 Step 9. 1. 1 v e r i f i e d by Licensed Operator.
/.
Signature /Date 9. 2 Review and Signoff 9.2.1 The calculations performed i n t h e following s t e p s on Attachment 2 have been independently v e r i f i e d :
8. 2. 3 c>
' 8. 2. 4
(-1 8. 2. 5
(->
L-'
8. 2. 6
(-1 Independent Verification
/
Signature /Date 9. 2. 2 T e s t completed.
/
Date/Time 9. 2. 3 T e s t personnel have recorded dose received and hours worked on Attachment 1.
9. 2. 4 Man-Rem and Man-Hours t o t a l l e d and recorded on Attachment 1.
Rev. No.
16
\\VI Page 22 o f 40
COMPUTER OUT OF SERVICE SURVEILLANCE ST-40C 10.0 ACCEPTANCE CRITERIA 10.1 Level 1 Acceptance Criteria 10.1.1 Avera e screenwell intake temperature is LESS THAN Avera e plant discharge water temperature is LESS Intake-dischar e differential temperature is LESS Average Drywell Temperature is LESS THAN OR EQUAL TO 135°F per Step 8.3.4.D.
Trend recorders listed shall be operable per Subsection 8.4.
OR EQ t AL TO 85°F per Step 8.2.4.
THAN 8 R EQUAL TO 112°F per Step 8.2.5.
THAN OR EQUAL f 0 32.4"F per Step 8.2.7.
10.1.2 10.1.3 10.1.4 10.1.5 I
10.1.6 Auxiliary operator plant tour logs have been completed per Subsection 8.5.
10.2 Level 2 Acceptance Criteria None L-Rev. No.
16 Page 23 of 40
COMPUTER OUT OF SERVICE SURVEILLANCE STT4OC 11.0 ACCEPTANCE VERIFICATION 11.1 P e r f o r m e r R e v i e w 11.1.1 Verify required data has been recorded and is within required tolerances.
(-1 een entered.
(-1 11.1.2 required i n i t i a l s and signatures 11.1.3 I F Level 1 Acceptance Criteria w a s not m e t,
THEN perform t h e following:
A.
B.
Immediately notify t h e CRS.
C.
I n i t i a t e a CR.
Sign off ST as unsatisfactory.
CR number D.
If necessary, i n i t i a t e a PID.
PID number L'
A CR is re uired f o r instruments t h a t exceed A s purposes.
IF only Level 2 Acceptance Criteria was not m e t,
THEN perform t h e following:
A.
8 NOTE :
ound tolerances f o r tracking 11.1.4 Sign o f f ST as s a t i s f a c t o r y with corrective actions.
B.
I n i t i a t e e i t h e r a CR o r a PID.
PID/CR number 11.1.5 Identify test r e s u l t s :
(-1 Satisfactory
(-1 Satisfactory with corrective actions
(-1 Unsatisfactory 11.1.6 Record r e s u l t s i n narrative log.
(-1 11.1.7 Sign and record date and t i m e.
Date/Time L-Rev. No.
16 Page 24 of 40
~
COMPUTER OUT OF SERVICE SURVEILLANCE ST-40C i-,
11.2 Management SRO Review 11.2.1 11.2.2 11.2.3 11 2. 4 11.2.5 11.2.6 11.2.7 Verify data is within required tolerances.
(-1 Verify data attachments, such as recorder printouts and c a l i b r a t i o n sheets are included as required.
(-1 Verif required i n i t i a l s and signatures have een entered.
(-1 Review test t o determine if test r e s u l t s s a t i s f y acceptance c r i t e r i a :
(-1 Satisfactory
(-1 Satisfactory with corrective actions
(-1 Unsatisfactory IF Level 1 acceptance criteria is not s a t i s f i e d,
TEEN immediately notify Operations Manager o r a l t e r n a t e. Record name of person n o t i f i e d.
Person Notified I n i t i a t e required corrective and compensatory actions.
(-) Not required
(-) Required Sign and record date and time.
Management SRO Date/Time Rev. No. 16 Page 25 of 40
I^..I-
.U" COMPUTER OUT OF SERVICE SURVEILLANCE ST - 40C 11.3 Remarks c
Rev. No. 16 Page 26 of 40
COMPUTER OUT OF SERVICE SURVEILLANCE ST-40C 12.0 ATTACHMENTS
- 1.
- 2.
3.
4.
5.
6.
TEST SIGNOFF LOG INTAKE, DISCHARGE, AND INTAKE-DISCHARGE DIFFERENTIAL TEMPERATURE CALCULATION DRYWELL TEMPERATURE CALCULATION RESISTANCE VS TEMPERATURE TABLE CIRC WATER RTD LIFTED LEAD CONTROL FORM DRYWELL RTD LIFTED LEAD CONTROL FORM Rev. No. 16 Page 27 of 40
COMPUTER OUT OF SERVICE SURVEILLANCE ST-40C I
Rev. No.
16 Page 28 of 40
(;
INTAKE. DISCHARGE, AND INTAKE-DISCHARGE DIFFERENTIAL TEMPERATURE CALCULATION CALC REF 36RTD-T e e 105B2 100 a PLATINUM 105A2 100 a PLATINUM 103AlB i o Q PLATINUM 103A2A i o Q PLATINUM 103BlA i o Q PLATINUM A
B C
-E
)ESC E
1R19 jCREENWELL INTAKE TEMP L
19DAS-14 SCREENWELL CNTAKE TEMP 3 9DAS - 14 2W INLET TEMP 3NDSR 33C-10A 0 9DAS - 15 2W INLET TEMP 2NDSR 33C-10A 09DAS - 15 CW INLET TEMP CNDSR 33C-10B 0 9DAS - 1 5
JEAD JO.
roe2 +
r082 -
roe2 P F128 +
F128 -
F128 P F130 +
F130 -
F130 P F133 +
F133 -
F133 P E+
1R18 TEMP Page 1 of 4
- Connection of leads only required after final set of temperature readings Time completed by I & C Performed by I&C Signature ST-40C COMPUTER OUT OF SERVICE SURVEILLANCE ATTACHMENT 2 Rev. No. 16 Page 29 of 40
103B2A 10 0 PLATINUM 106A 100 D PLATINUM 106B 100 Q PLATINUM 106C 100 Q PLATINUM 106D 100 0 PLATINUM INTAKE. DISCHARGE. AND INTAKE-DISCHARGE DIFFERENTIAL TEMPERATURE CALCULATION DESC T.B TEMP CALC REF F
TERM LEAD NO.
CABINET CW INLET TEMP CNDSR 33C-10B
~
18 F136 +
F136 -
1R18 1R18 19 20 F136 P 0 9DAS - 1 5
lRl8 1R17 i ~ i 7
PLANT DISCHARGE WATER A TEMP TlOO +
TlOO -
TlOO P 1R17 0 9DAS - 14 PLANT DISCHARGE WATER B TEMP TlOl +
1R17 TlOl -
1R17 5
TlOl P 1R17 0 9DAS - 14 6
7 PLANT DISCHARGE WATER C TEMP T102 -+
1R17 T102 -
1R17 8
T102 P T103 +
T103 -
T103 P 1R17 1R17 1R17 1R17 9
10 0 9DAS - 14 PLANT DISCHARGE WATER D TEMP 11 12 0 9DAS - 14 I
Performed by I&C Signature ST-40C COMPUTER OUT OF SERVICE SURVEILLANCE ATTACHMENT 2 Rev. No. 16 Page 30 of 40
L-ST-40C COMPUTER OUT OF SERVICE SURVEILLANCE ATTACHMENT 2 Rev. No.
16 Page 31 of 40 NOTE :
Average screenwell intake temperature l i m i t is 435°F.
Avera e Screenwell Intake Temperature
(
A
+
B
)
= Ave Screenwell 8. 2. 3 Calcu !?
ation 2
Intake Temp d
"F
+
2 (185 OF)
I n i t 8.2.4 Avera e Circulating Water I n l e t Temperature Calcu !f ation
(
C
+
D
+
E
+
F
)
= Ave Circ 4
Water I n l e t Temp
(
"F
+
+
+
4 I n i t Avera e plant discharge water temperature l i m i t is
<112".
Avera e Plant Discharge Water Temperature I?
Calcu f ation NOTE :
8.2.5
(
G
+
H
+
I
+
J
)
= Ave Plant Disch 4
Water Temp
(
"F
+
+
+
4 (51 12°F)
I n i t
NOTE :
Intake-discharge differential temperature limit is 532.4"F.
8.2.6 Intake-Discharge Differential Temperature Calculation NOTE: Step A o r B may be marked "NA" if A.
not applicable.
Circulating inlet water tempering in progress differential temp (8.2.5 - 8. 2. 4 ) = intake-discharge
(
> =
"F (132.4"F)
E.
Circulating inlet water tempering not in progress (8.2.5 - 8. 2. 3 ) = intake-discharge differential temp
> =
"F (i32.4"F)
(
Init Init ST-40C COMPUTER OUT OF SERVICE SURVEILLANCE ATTACHMENT 2 Rev. No.
16 Page 32 of 40 i/
L--
DRYWELL AREA 0
I I
I RTD READING FACTOR CORRECTED VALUE 16-1RTD-(-1 1 0 1 0.1133
(-1 1 2 0 (3 1 1 2
(-1 1 1 8 7
0. 0 6 2 1 SUM OF USED WEIGHTING FACTORS:
SUM OF CORRECTED VALUES:
AVERAGE DRYWELL TEMPERATURE:
~ 1 3 5 ° F ST-40C COMPUTER OUT OF SERVICE SURVEILLANCE ATTACHMENT 3 Rev. N o.
1 6 Page 33 of 40
V' Temperature O
F 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 Rev. No.
16 RESISTANCE VS TEMPERATURE TABLE 1OD Platinum RTD Alpha = 0.00385 O / Q / O C Resistance Ohms 10.00 10.02 10.04 10.07 10.09 10.11 10.13 10.15 10.17 10.20 10.22 10.24 10.26 10.28 10.30 10.33 10.35 10.37 10.39 10.41 10.43 10.46 10.48 10.50 10.52 10.54 10.56 10.59 10.61 10.63 10.65 10.67 10.69 10.72 10.74 10.76 10.78 10.80 10.82 10.84 10.87 10.89 10.91 Temperature "F
75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 100 101 102 103 104 105 106 107 108 109 110 111 112 113 114 115 116 117 Resistance Ohms 10.93 10.95 10.97 11.oo 11.02 11.04 11.06 11.08 11.10 11.12 11.15 11.17 11.19 11.21 11.23 11.25 11.28 11.30 11.32 11 - 3 4 11.36 11.38 11.40 11.43 11.45 11.47 11.49 11.51 11.53 11.55 11.58 11.60 11.62 11.64 11.66 11.66 11.68 11.70 11.73 11.75 11 -77 11.79 11.81 Page 34 of 40
Temperature "F
118 119 120 121 122 123 124 125 126 127 128 129 130 Rev. No.
16
- 14.
RESISTANCE VS TEMPERATURE TABLE 109 Platinum RTD Alpha = 0.00385 Q / Q / O C Resistance Ohms 11.83 11.88 11.90 11.92 11.94 11.96 11.98 12.00 12.03 12.05 12.07 12.09 12.11 Page 35 of 40
f '
i ATTACHMENT 5 CIRC-WATER RT_D_.LI FTED LEAD CONTROL FORM Page 1 of 2 T. B.
LEAD NO.
TERM LEAD LABEL D AND TAGGED (Steps 8. 2 2.A and 8.2.2. B) t DESC
- LEAD RECO:\\TNECTED AND TAG REMOVE:)
(Steps 8.9.3.A and 8.9.3. B)
PERFORMED INDEPENDENT BY VERIFICATION Signature Signature CABINET I
PERFORMED INDEPENDENT VERIFICATION
--I---
Signature Signature PERFORMED CONCURRENT BY DUAL VERIFICATION Signature Signature TO83 +
1R18 l R 1 8 -
SCREENWELL INTAKE TEMP 09DAS-14 13 1 4 I
~~
TO83 -
lRl8 l R l 8 -
15
~ o a 3 P
TO82 +
TO82 -
TO82 P 18 SCREENWELL INTAKE TEMP 1 9 l R l 8 1 R 1 8 2 0 09DAS-14 CW INLET TEMP CNDSR 3 3 C-1 OA F128 +
1R18 1R18 -
4 +
F 1 2 8 -
5 1R18 1 R 1 9 -
6 F 1 2 8 P F130 +
0 9DAS - 1 5 2W INLET TEMP CNDSR 3 3C-1 OA 1
1 R 1 9 1 R 1 9 -
2 F 1 3 0 -
F 1 3 0 P 3
0 9DAS - 1 5 ZW INLET TEMP CNDSR 33C-1 0 B F133 +
1 R 1 9 1 R 1 9 -
10 11 F 1 3 3 -
1 R 1 9 -
1 2 F 1 3 3 P 0 9DAS - 1 5
- Connection of leads only required after final set of temperature readings Rev. No.
16 Page 36 of 40
P a g e 2 of 2 ATTACHMENT 5 CIRC WATER RTD LIFTED LEAD CONTROL FORM DESC CABINET T.B.
LEAD LABEL D AND TAGGED (Steps 8.2 2.A and 8. 2. 2. B) I
- LEAD RECOTNECTED AND TAG REMOVE)
(Steps 8. 9. 3. A and 8.9.3.B)
PERFORMED INDEPENDENT BY VERIFICATION LEAD NO.
F136 +
F136 -
TERM 18 (Step 8.2.
I I
VERIFICATION VERIFICATION CW INLET TEMP CNDSR 33C-1 OB 1R18 1R18 -
--I----
+
1 9 F136 P 1R18 1R17 -
20 +
0 9DAS - 1 5 1
PLANT DISCHARGE WATER A TEMP 0 9DAS - 14 TlOO +
TlOO -
TlOO P 1R17 1R17 1R17 l R 1 7 7
2 + +
3 T l O l +
4 --I---
+
PLANT DISCHARGE WATER B TEMP 0 9DAS - 14 PLANT DISCHARGE WATER C TEMP 09DAS - 14 PLANT DISCHARGE WATER D TEMP 09DAS - 14 T l O l -
5 T l O l P 1R17 1R17 1R17 1R17 1R17 6
T 1 0 2 +
7 8
T 1 0 2 -
9 T 1 0 2 P T 1 0 3 +
T 1 0 3 -
10 1R17 1R17 -
11 12 T 1 0 3 P
- C o n n e c t i o n of leads only required after final set of temperature readings Rev. No.
16 Page 37 of 3
S T - 4 0 C COMPUTER OUT OF SERVICE SURVEILLANCE ATTACHMENT 6 DRYWELL RTD LIFTED LEAD CONTROL FORM Page 1 of 2 Connection of leads only required after final set of temperature readings 4
R e v. No.
16 Page 38 of 40
i S T - 4 0 C COMPUTER OUT OF SERVICE SURVEILLANCE ATTACHMENT 6 DRYWELL RTD LIFTED LEAD CONTROL FORM Page 2 of Connection of leads only required after final set of temperature readings R e v. N o.
16 Page 39 of 40
COMPUTER OUT OF SERVICE SURVEILLANCE ST-4OC ATTACHMENT 6 DRYWELL RTD LIFTED LEAD CONTROL FORM Page 3 of Connection of leads only required after final set o f temperature readings R e v. No.
16 Page 40 of.40
James A. FibPatrick Nuclear Power Plant Nuclear Northeast OPERATIONS TRAINING PROGRAMS S/RO NEW TASK TITLE: EVALUATE SURVEILLANCE TEST APPL. TO JPM NUMBER ACCEPTANCE CRITERIA REV: 0 DATE: 5/23/03 NRC WA SYSTEM NUMBER:,/
JAF TASK NUMBER:
JAF QUAL STANDARD NUMBER:
ESTIMATED COMPLETION TIME: 20 Minutes SUBMITTED:
~
1 OPERATION REVIEW:
\\
APPROVED:
CANDIDATE NAME:
S.S. NUMBER:
JPM Completion:
( ) Simulated
( )Performed Location :
( ) Plant
( )Simulator DATE PERFORMED:
TIME TO COMPLETE: -
Minutes PERFORMANCE EVALUATION:
( ) Satisfactory
( ) Unsatisfactory EVALUATOR:
SIGNATURE/PRINTED CANDIDATE REV1 E W:
SIGNATURE REVIEWED BY:
PROGRAM ADMINISTER L
DOC. COMPLETE:
Page 1 of 5
JOB PERFORMANCfE MtASUKt RECORD AND CHECKLIST NEW TASK TITLE: EVALUATE SURVEILLANCE TEST ACCEPTANCE CRITERIA APPL. TO JPM NUMBER Current Update: 5/23/03 By: RVVD Date Int.
Outstanding Items:
Technical Review Additional Information Questions and Answers Procedural Change Required Validation
~
None Comments:
I Previous Revision Dates:
Page 2 of 5
JOB PERFUKMANLE fik~aunc REQUIRED TASK INFORMATION NEW TASK TITLE: EVALUATE SURVEILLANCE TEST ACCEPTANCE CRITERIA APPL. TO JPM NUMBER
- 1.
SAFETY CONSIDERATIONS A.
Ensure proper safety equipment and safety procedures are observed.
II.
REFERENCES A.
- 6.
AP-19.01, SURVEILLANCE TESTING PROGRAM C.
AP-03.11, OPERABlLlN AND REPORTABILITY DETERMINATIONS ST-01 6, MSlV FAST CLOSURE TEST 111.
TOOLS AND EQUIPMENT A.
None IV.
SET UP REQUIREMENTS
'v A.
B.
Best if conducted in the Control Room or the simulator.
If performed in alternative locations, normal controlled references and prints may need to be available.
V.
EVALUATOR NOTES A.
If performing JPM in the plant, inform the candidate that the conditions of each step need only be properly identified and nat actually performed.
B.
The candidate should, at a minimum, identify the change in equipment status light indication when equipment operation is simulated.
VI.
TASK CONDITIONS A.
- 6.
Candidate will review a completed ST-01 B Surveillance Test containing test failure data that was not recorded by the performer.
- - CRITICAL STEP L
Page 3 of 5
SIROINLO TASK TITLE:
STANDARD Candidate review all data recorded in Surveillance Test.
Candidate may determine that step 8.4.3 does not meet acceptance criteria.
Candidate review all initiakignature blocks for completion Candidate will recognize that step 8.4.3 does not meet acceptance criteria and therefore check the Unsatisfactory box EyALUATOR When indicated, Acknowledge as the CRS and report PID and CR are being written VII.
INITIATING CUE EVALUATION I COMMENT SAT I UNSAT SAT I UNSAT SAT I UNSAT You are the Senior Nuclear Operator (SNO). Another SNO has just completed ST-01 B, MSlV FAST CLOSURE TEST, and forwards it to you to complete the SNO review.
Candidate will recognize that step 8.4.3 does not meet acceptance criteria and therefore check the Unsatisfactory box EVALllATOR Hand copy of completed Surveillance Test to candidate.
SAT/UNSAT I.
- 2.
- 3.
- 4.
- 5.
STEP 1 1.1. I Verify required data has been
-ecorded and is within required iolerances.
11. I.2 Verify required initials and signatures have been entered.
1 1.I
.3 IF Level 1 Acceptance Criteria OR Level 2 LLRT valve acceptance criteria was not met, THEN perform the following:
A. Sign off ST as unsatisfactory.
B. Immediately notify the CRS.
C. Initiate a DER.
D. If necessaw, initiate a PID.
11. I.4 IF only Level 2 Acceptance Criteria was not met, THEN perform the following:
A. Sign off ST as satisfactory with corrective actions.
B. Initiate either a DER or a PID.
PIDIDER number 1 1.1.5 Identify test results:
(J Satisfactory Satisfactory with corrective actions 1 Unsatisfactorv SAT I UNSAT This step is not applicable I
Page 4 of 5
STEP STANDARD EVALUATION / COMMENT I
1 I
I 1.I
.6 Sign and record date and time.
Candidate will sign, date and time the surveillance test EVALUATOR When prompted by candidate, indicate that the SNO loa entrv is beina made.
EVALUATOR: Terminate the task at this point.
1
- 6.
11.I
.7 Record results in SNO log.
- 7.
! j
?
Page 5 of 5
L,
- t****************C******
TSR CONTINUOUS USE TECHNICAL
~
ENTERGY NUCLJ3A.R OPERATIONS, INC.
JAMES A. FITZPATRICK NTJCLEAR POWER PLAN" OPERATIONS SURVEILLANCE TEST PROCEDURE MSIV FAST CLO-TEST (IST)
ST-1B REVISIOH 23 f
APPROVED BY:
PROCEDURE 6-EFFECTIVE DATE :
lo-/q-Oa LIMITED REVISION PO FIRST ISSUE 0 FULL REVISION n
- t****************C******
TSR CONTINUOUS USE TECHNICAL
'V ST-1B MSIV FAST CLOSURE TEST (ISTI REV 23 22 21 20 NO.
REVISION
SUMMARY
SHEET CHANGE AND REASON FOR CHANGE Added clarification to frequency that valves tested at a cold shutdown frequency may include valves tested while decreasing power to cold shutdown or while increasing power to steady state power operation (NUREG-1482 Section 3.1.1.1 supporting PCR dated 5/16/02)
Revised prerequisites to change plant condition to E2x Pressure e 5psig to allow testing prior to cold shutdown to minimize MSIV dry stroking (PCR dated 5/16/02)
Revised prerequisite on water level to include option of New GE REM Steam line plugs installed and steam lines drained, allows performance earlier in outage(PCR dated 4/19/02)
Revised Section 8 and Section 9 to include provisions for MSIVs remaining closed per OF-65 (PCR dated 5/16/02)
Revised prerequisite to refer to Reactor Mode for support of ITS.
Made changes to the Operations Department Operating Shift Organization titles per FYI #02-005 throughout. Changes not rev barred.
Deleted the requirement to record calibration due date in Sections 4 and 5 per ODSO-31.
Revised Section 11 to eliminate SM and Assistant Operations Manager review and replaced with one review by a Management SRO. This change reduces the administrative burden of multiple independent reviews. Change made with Rev. 23 to AP-02.01.
Revised Section 1.2 to include Improved Technical Specification references.
Deleted Tech Spec frequency of quarterly and updated Tech Spec surveillance references in Subsection 1.2.1 to reflect Tech Spec Amendment 242. (PCR #1 dated 2/24/99)
Full revision to reflect change to IST program to perform MSIV fast closure at Cold Shutdown. Also deleted testing of 29MOV-74 and 29MOV-77 (relocated to ST-1C) and updated procedure title.
Rev. No 23 24 Page 2 of
MSIV FAST CLOSURE TEST ( I S T )
ST-1B TABLE OF CONTENTS PAGE SECTION 1.0 REQUIREMENTS 4
6 2.0 PURPOSE..................... -.. -
6
3.0 REFERENCES
7 4.0 PREREQUISITES.............. -........
8 5. 0 TEST EQUIPMENT, SPECIAL TOOLS, AND MATERIALS 8
6.0 PRECAUTIONS AND LIMITATIONS................
7.0 GENERAL TEST METHODS 10 8.0 PROCEDURE.........................
11 8.1 MSIV 29AOV-80A Test.... -...............
11 8.2 MSIV 29AOV-86A Test....................
11 8.3 MSIV 29AOV-80B Test..... -..............
12 8.4 MSIV 29AOV-86B Test....................
12 8.5 MSIV 29AOV-80C Test....................
13 8.6 MSIV 29AOV-86C Test....................
13 8.7 MSIV 29AOV-80D Test....................
14 8.8 MSIV 29AOV-86D Test....................
14 9.0 RETURN TO NORMAL 15 1 0. 0 ACCEPTANCE CRITERIA....................
18 1 1. 0 ACCEPTANCE VERIFICATION -.................
1 9 12.0 ATTACHMENTS........................
23
- 1.
TEST SIGNOFF LOG 24 Rev. No. 23 24 Page 3 of
ST-1B MSIV FAST CLOSURE TEST (ISTI 1.0 REQUIREMENTS 1.1 Frequency
?COM1.4.1 IST cold shutdown testing shall be performed as follows:
Valve exercising shall commence within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of achieving cold shutdown, and continue until a l l testing is complete or the plant is ready to return to power.
Completion of all cold shutdown testing is not a prerequisite to plant startup, provided testing began within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of achieving cold shutdown. Any testing not completed during one cold shutdown shall be scheduled first during the next cold shutdown.
For extended outages, testing need not begin within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided all valves that are required to be tested during cold shutdown are tested before plant startup.
Valves tested at a cold shutdown frequency may include valves tested while decreasing power to cold shutdown or while increasing power to steady state power operation.
Cold shutdown tests are not required if satisfactorily completed within the past 3 months (92 days).
Cold shutdown tests shall be completed before startup from a Refueling Outage, unless test has been completed within the past 3 months (92 days).
Rev. No. 23 Page 4 of 24
1.2 l-4.
1.3 1.4 1.5 Technical Spocificati~s 1.2.1 surwillarrrse Rsquiraeat.
r SR 3.6.1-3.7 is satisfied by completion of ST-IB and ST-1D.
Partially satisfies SR 3.6.1.3.7 1.2.2 Limiting CorrClitioxm for m a t i a n LCO 3.6..1.3 Other ASME Section XI 1989 Edition no addenda 1.4.1 JAFNPP Inservice Testing Program for Pumps and Valves, C o l d Shutdown Justification CSJ-018 defers testing of MSIVs to cold shutdown.
=xxmctatioPlrr None Rev. No.
23 Page 5 of 24
ST-1B 2.0 3.0 3.1 3.2 PURPOSE To test MSIVs as required by the IST Program.
REFERENCES Performance References None Developmental References 3.2.1 3.2.2 3.2.3 3.2.4 3.2.5 3.2.6 3.2.7 3.2.8 3.2.9 3.2.10 3 -2.11 3.2.12 Rev. No. 23 ODSO-32, Shutdown Procedure OP-1, Main Steam System ASME Section XI 1989 Edition no addenda Inservice Testing Program For Pumps and Valves, Third Interval AP-19.05, Pump and Valve Inservice Testing ESK-7A, 7B FM-29A 1.67-97 thru 98 1.70-98 thru 110 AP-01.04, Tech Spec Related Requirements, Lists and Tables NUREG-1482 Guidelines for Inservice Testing at Nuclear Power Plants, Section 3.1.1.1 JD-01-123, GE REM Light Dryer Wet Transfer System 24 Page 6 of
ST-1B MSIV FAST CLOSURE TEST (IST)
NOTE:
Sections 4 and 5 may be performed in any order or concurrently.
Init 4.0 PREREQUISITES 4.1 SM has granted permission to perform this test.
4.2 Revision Number of this Working Copy is the same as the '2 revision number listed in the Master Copy of the Index of Operations Surveillance Test Procedures.
4.3 Test personnel have read this procedure and are thoroughly familiar with its contents.
C-L y c.1 4.4 Start of test recorded.
I i O c
C q
is t c
4Dake/Time n
4.5 Start of test recorded in SNO Log.
A!
4.6
[CTSI Reactor is shutdown, Reactor Pressure c5 psig.
[ I T S ]
Reactor is in Mode 3, 4 or Mode 5, Reactor Pressure e 5 psig.
J ? '
4.7 RPV Water Level is LESS THAN 270 inches or GE REM Main Steam Line plugs installed with steamlines drained.
4.8 Calibration for each instrument listed in Subsection 5.1 is up-to-date.
4 4.9 IF ST-41D, Remote Valve Position Indication Verification (IST), is in progress, THEN performance of this test has been coordinated with the performance of ST-41D.
4 4 Rev. No. 23
. I MSIV FAST CLOSURE TEST ( I S T )
ST-1B L--
5.0 5.1 5.2 5.3 6.0 6. 1 6.2 Rev.
TEST EQUIPMENT, SPECIAL TOOLS, AND MATERIALS Test Equipment Stopwatch ec/ I Serial Number Special Tools None Ma t e r i a1 s None PRECAUTIONS AND LIMITATIONS Precautions None Limitations 6.2.1 Test personnel shall immediately notify the SNO or CRS of any failure to meet acceptance criteria.
6.2.2 Test personnel shall print name, sign initials, and enter date on Attachment 1 before performing Section 8 of this test.
6.2.3 When test personnel complete their assigned portion of this test, they shall enter hours worked on.
6.2.4 Once this test has been started, any additional test personnel shall read this procedure and become thoroughly familiar with its contents before performing any portion of this test.
No. 23 Page 8 of 24
L-MSIV FAST CLOSURE TEST (IST)
ST.- 1B 6.2.5 Multiple working copies of this test may be used provided the following requirements are satisfied:
NOTE:
The work site is defined as the location where work is controlled. The location of the work site is at the discretion of the SNO.
A. A working copy of this test shall be retained at the work site.
B. The work site working copy shall be the legal record for documenting this test.
C. Data from all steps performed away from the work site, including signatures, initials, and recorded values, is transcribed into the work site working copy following completion of test.
6.2.6 Conditional (IF, THEN) steps in this test may be marked eNAtl if not applicable.
6.2.7 Steps in this test marked eNR1t are not required to be initialed.
Rev. No. 23 Page 9 of 24
ST-1B 7.0 7.1 7.2 7.3 7.4 GENERAL TEST METHODS This test consists of eight subsections which test MSIVs as required by the IST Program.
Subsections 8.1 through 8. 8 may be performed in any order as necessary to facilitate plant operations or maintenance.
Steps within each subsection shall be performed in the order specified.
Valve closing times are measured from when the control switch is placed in close until the red open indicating light goes off. IST limits are listed as (IST:). Tech Spec time limits are listed as (TS:).
This procedure may be used for post-work testing and verification of operability for applicable equipment provided the following actions are performed:
7.4.1 The actions and requirements of Sections 1 through 6, 10, and 11 are satisfied.
7.4.2 The applicable portions of Sections 8 and 9 are performed.
7.4.3 Signoffs for non-applicable portions of Sections 8 and 9 are marked "NA". Non-applicable subsections may be marked "NAl' by drawing a diagonal line on each page and marking the page "NA".
7.4.4 The reason for partial performance of this test is documented in Subsection 11.4.
Rev. No. 23 Page 10 of 24
~
-_.I_...-.
ST-1B Init 8.0 PROCEDURE 8.1 MSIV 29AOV-80A Test 8.1.1 Record as-found position of MSIV 29AOV-80A.
C p 4 (posit ion) 8.1.2 Ensure open MSIV 29AOV-80A.
8.1.3 Close and time MSIV 29AOV-80A.
Closing time
- 4. 7 secs (IST: 3 to 5 secs)
(TS: 3 to 5 secsl 8.1.4 IF desired to have valve remain closed per Section F of OP-65, THEN mark the following step (N/A).
8.1.5 Ensure MSIV 29AOV-80A is in the as-found position recorded in Step 8.1.1.
8.2 ISIV 29AOV-86A Test 8.2.1 8.2.2 8.2.3 8.2.4 8.2.5 Rev. No.
23 Record as-found position of MSIV 29AOV-86A.
cqc rJ (position)
Close and time MSIV 29AOV-86A.
Closing time
.c/. J/
secs (IST: 3 to 5 secs)
(TS:
3 to 5 secs)
IF desired to have valve remain closed per Section F of OP-65, THEN mark the following step (N/A).
Ensure MSIV 29AOV-86A is in the as-found position recorded in Step 8.2.1.
J!
Q n/ in-Page 11 of 24
ST-1B MSIV FAST CLOSURE TEST (IST) 8.3 MSIV 29AOV-80B T e s t 8.3.1 Record as-found position of MSIV 29AOV-80B.
c; (posit ion) 8.3.2 Ensure open MSIV 29AOV-80B.
8.3.3 Close and time MSIV 29AOV-80B.
Closing time 7 t C-secs (IST: 3 to 5 secs)
(TS: 3 to 5 secs) 8.3.4 IF desired to have valve remain closed per Section F of OP-65, THEN mark the following step (N/A).
8.3.5 Ensure MSIV 29AOV-80B is in the as-found position recorded in Step 8.3.1.
8.4 MSIV 29AOV-86B T e s t 8.4.1 8.4.2 8.4.3 8.4.4 8.4.5 Record as-found position of MSIV 29AOV-86B.
OpcJ (posit ion)
Init 2
r,
x Close and time MSIV 29AOV-86B.
Closing time
.C secs
( I S T : 3 to 5 secs)
(TS: 3 to 5 secs)
IF desired to have valve remain closed per Section F of OP-65, THEN mark the following step (N/A).
Ensure MSIV 29AOV-86B is in the as-found position recorded in Step 8.4.1.
Rev. No. 23 Page 12 of 24
ST-1B MSIV FAST CLOSURE TEST (IST)
Init 8.5 MSIV 29AOV-80C T e s t 8.5.1 Record as-found position of MSIV 29AOV-80C.
COCA
( pos'i t ion) 8.5.2 Ensure open MSIV 29AOV-80C.
8.5.3 Close and time MSIV 29AOV-80C.
secs
.? c\\
Closing time (IST: 3 to 5 secs)
(TS: 3 to 5 secs) 8.5.4 IF desired to have valve remain closed per Section F of OP-65, THEN mark the following step (N/A).
8.5.5 Ensure MSIV 29AOV-80C is in the as-found position recorded in Step 8.5.1.
8.6 MSIV 29AOV-86C T e s t 8.6.1 8.6.2 8.6.3 8.6.4 8.6.5 Record as-found position of f - l MSIV 29AOV-86C.
cp+
(posit ion)
Close and time MSIV 29AOV-86C.
Closing time 4.- I secs (IST: 3 to 5 secs)
(TS: 3 to 5 secs)
IF desired to have valve remain closed per Section F of OP-65, THEN mark the following step ( N / A ).
Ensure MSIV 29AOV-86C is in the as-found position recorded in Step 8.6.1.
J?
Rev. No. 23 24 Page 13 of
ST.-
1 B Init 8.7 YSIV 29AOV-80D T e s t
'L 8.7.1 Record as-found position of MSIV 29AOV-80D.
G,pF 3 (pos it ion1 8.7.2 Ensure open MSIV 29AOV-80D.
8.7.3 Close and time MSIV 29AOV-80D.
Closing time
- 7.
secs (IST: 3 to 5 secsl (TS: 3 to 5 secs) 8.7.4 IF desired to have valve remain closed per Section F of OP-65, THEN mark the following Step (N/A).
8.7.5 Ensure MSIV 29AOV-80D is in the as-found position recorded in Step 8.7.1.
8.8 MSIV 29AOV-86D T e s t 8.8.1 Record as-found position of MSIV 29AOV-86D.
8.8.2 Ensure open MSIV 29AOV-86D.
8.8.3 Close and time MSIV 29AOV-86D.
Closing time 4 7 secs (IST: 3 to 5 secs)
(TS: 3 to 5 secs) 8.8.4 IF desired to have valve remain closed per Section F of OP-65, THEN mark the following step (N/A).
8.8.5 Ensure MSIV 29AOV-86D is in the as-found position recorded in Step 8.8.1.
J?
Rev. No. 23 Page 14 of 24
ST-1B 9.0 RETURN TO NOEudAL Init 9.1 System R e s t o r a t i o n 9.1.1 IF MSIVs remained closed per OP-65 Section F, THEN each MSIV is closed:
MSIV 29AOV-80A MS IV 2 9AOV - 8 6A MSIV 29AOV-80B MSIV 29AOV-86B MSIV 29AOV-80C MSIV 29AOV-86C MSIV 29AOV-80D MSIV 29AOV-86D 9.1.2 IF MSIVs were not closed per OP-65 Section F, THEN each MSIV is in the as-found position recorded in the specified step:
MSIV 29AOV-80A is in the position recorded in Step 8.1.1 MSIV 29AOV-86A is in the position recorded in Step 8.2.1 MSIV 29AOV-80B is in the position recorded in Step 8.3.1 MSIV 29AOV-86B is in the position recorded in Step 8.4.1 MSIV 29AOV-80C is in the position recorded in Step 8.5.1 MSIV 29AOV-86C is in the position recorded in Step 8.6.1 MSIV 29AOV-80D is in the position recorded in Step 8.7.1 MSIV 29AOV-86D is in the position recorded in Step 8.8.1 Rev. NO. 23 Page 15 of 24
S T - 1 B MSIV FAST CLOSURE TEST (IST) 9.1.3 IF a l l MSIVs are open, THEN the f o l l o w i n g MSIV CLOSURE T R I P relays are energized 5A-K3E 5A-K3A 5A-K3C 5A-K3G 5A-K3 F 5A-K3B 5A-K3D 5A-K3H a t pane 1 a t panel a t panel at panel a t panel a t pane 1 a t panel a t panel 09-15 09-15 09-15 09-15 09-17 09-17 09-17 09-17 9.1.4 Steps 9.1.1 through 9.1.3 verified by L i c e n s e d O p e r a t o r.
R e v. N o.
23 24 Page 1 6 of
.W MSIV FAST CLOSURE TEST (IST)
ST-1B Init 9. 2 Review and Signoff 9.2.1 Test completed. T C
C L
y
/
49iJ Date /+ihe 9.2.2 Test personnel have recorded hours worked on.
9.2.3 Man-Hours totalled and recorded on.
Rev. No.
23 Page 17 of 24
MSIV FAST CLOSURE TEST ( I S T )
ST-1B I S T Stroke Time Tech Spec Va Ive (secs)
Stroke Time (secsl r
10.0 ACCEPTANCE CRITERIA Step 10.1 Level 1 Acceptance Criteria 2 9AOV-8 OB 3 to 5 3 t o 5 2 9AOV-8 6 B
3 t o 5 3 t o 5 29AOV-80C 3 t o 5 3 t o 5 29AOV-86C 3 t o 5 3 t o 5 Each t e s t e d valve was cycled and closed within the following stroke time l i m i t s :
8.3.3 8.4.3 8.5.3 8.6.3 29AOV-86D 3 t o 5 I
8.1.3 I
3 t o 5 I
3 t o 5 I
3 t o 5 8.8.3 I
3 t o 5 3 t o 5 I
8.7.3 I
I L,
I f a valve stroke time does not meet the I S T l i m i t, the valve s h a l l be declared inoperable and applicable LCO actions s h a l l be taken.
An I S T evaluation which determines t h a t valve operation i s acceptable may be used t o restore the valve t o an operable s t a t u s i f Tech Spec l i m i t s are not exceeded.
10.2 Level 2 Acceptance Criteria None Rev. N o.
23 Page 18 of 24
ST-1B MSIV FAST CLOSURE TEST (IST)
'e 11.0 ACCEPTANCE VERIFICATION 11.1 SNO R e v i e w
'L-11.1.1 Verify required data has been recorded and is within required tolerances.
Verify required initials and signatures have been entered.
IF Level 1 Acceptance Criteria OR Level 2 LLRT valve acceptance criteria was not met, THEN perform the following:
A. Sign off ST as unsatisfactory.
11.1.2 11.1.3 B. Immediately notify the CRS.
C. Initiate a DER.
D. If necessary, initiate a PID.
DER number PID number NOTE :
A DER is required for instruments that exceed As Found tolerances for tracking purposes.
IF only Level 2 Acceptance Criteria was not met, THEN perform the following:
A.
11.1.4 Sign off ST as satisfactory with corrective actions.
B. Initiate either a DER or a PID.
PID/DER number 11.1.5 Identify test results:
(-1 Satisfactory
(-1 Satisfactory with corrective actions
(-1 Unsatisfactory 11.1.6 Sign and record date and time Date /Time SNO
(-1 11.1.7 Record results in SNO log.
Rev. No. 23
~~
ST-1B MSIV FAST CLOSURE TEST (IST) 11.2 Management SRO Review 11.2.1 11.2 - 2 11.2 - 3 11.2.4 11.2.5 11.2.6 11.2.7 Verify data is within required tolerances.
Verify data attachments, printouts and calibration sheets are such as recorder included as required.
(-1 been entered.
(-)
Verify required initials and signatures have Review test to determine if test results satisfy acceptance criteria:
(-)
Satisfactory
(-1 Satisfactory with corrective actions
(-1 Unsatisfactory IF Level 1 acceptance criteria is not satisfied, THEN immediately notify Operations Manager or alternate. Record name of person notified.
Person Notified Initiate required corrective and compensatory actions.
(-1 Not required
(-)
Required Sign and record date and time.
Manage me n t S RO Date /Time Rev. No. 23 Page 20 of 24
ST-1B 11.3 IST Coordinator Review 11.3.1 Review t e s t r e s u l t s.
11.3.2 Update records as required.
I S T Coordinator Rev. No.
23 Date /Time Page 21 of 24
ST-1B 11.4 Remarks Rev. NO.
2 3 Page 22 of 24
MSIV FAST CLOSURE TEST ( I S T )
ST-1B 12. 0 ATTACHMENTS
- 1.
TEST SIGNOFF LOG Rev. No.
23 Page 2 3 of 24
ST-1B MSIV FAST CLOSURE TEST ( I S T )
ATTACHMENT 1 Page 1 of 1 TEST SIGNOFF LOG Rev. No.
2 3 2 4 Page 24 of
-mh -
Entwo James A. FitzPatrick Nuclear Power Plant Nuclear Northeast OPERATIONS TRAINING PROGRAMS SlRO NEW TASK TITLE: ST-5D APPL. TO JPM NUMBER REV: 0 DATE: 5/26/03 JAF TASK NUMBER:
NRC WA SYSTEM NUMBER: 7 1.7 3 7l4.4 JAF QUAL STANDARD NUMBER:
ESTIMATED COMPLETION TIME: 20.
Minutes SUBMITTED:
OPERATION REVIEW:
APPROVED:
CANDIDATE NAME:
S.S. NUMBER:
JPM Completion:
(
) Simulated
( X ) Performed Location:
(
) Plant
( X ) Simulator DATE PERFORMED:
TIME TO COMPLETE: -
Minutes PERFORMANCE EVALUATION:
( ) Satisfactory
( ) Unsatisfactory EVALUATOR:
S IG NATU RE/PRI NTE D CANDIDATE REVIEW:
SIGNATURE REVIEWED BY:
PROGRAM ADMINISTER DOC. COMPLETE:
Page 1 of 7
i-S/RO NEW TASK TITLE: ST-5D APPL. TO JPM NUMBER Current Update: 5/26/03 Date By: RWD Int.
Outstanding Items:
Technical Review Questions and Answers Procedural Change Required Additional Information Validation
___ None Comments:
Simulator validated 5/24/03. IC-I 33 Previous Revision Dates:
Page 2 of 7
LS/RO NEW TASK TITLE: ST-5D APPL. TO JPM NUMBER I.
- 11.
111.
IV.
\\-
- v.
VI.
SAFETY CONSIDERATIONS A.
Ensure proper safety equipment and safety procedures are observed.
REFERENCES A.
B.
ST-5D, APRM CALIBRATION, Rev. 2 OP-16, NEUTRON MONITORING, Rev. 24 TOOLS AND EQUIPMENT A.
Small Screwdriver SET UP REQUIREMENTS A.
B.
C.
>25% CTP IC with 2 loops in service, EPIC available and plant conditions stable.
Adjust all APRMs to an acceptable value per ST-5D.
Adjust desired APRMs to >2% above or below desired value of ST-5D.
EVALUATOR NOTES A.
- 6.
C.
If performing JPM in the plant, inform the candidate that the conditions of each step need only be properly identified and nat actually performed.
The candidate should, at a minimum, identify the change in equipment status light indication when equipment operation is simulated.
This JPM performance data based upon E and D APRMs initially 34% low at -98% CTP TASK CONDITIONS A.
Plant returning to 100% CTP following rod pattern exchange. Currently at -98 % CTP.
- 6.
ST-5D required prior to continuing to 100% CTP.
- - CRITICAL STEP u
Page 3 of 7
(
S/RO/NLO NEW VII.
INITIATING CUE TASK TITLE: ST-5D STANDARD You are the SNO. The plant is currently operating at -98% CTP following a rod pattern exchange with no equipment out of service. The plant has been stable for several minutes. ST-SD, APRM CALIBRATION is required prior to continuing to 100% CTP. Perform ST-5D.
EVALUATION I COMMENT EVALUATOR Hand partially completed ST-5D to candidate
- 1.
- 2.
- 3.
STEP
~~ -~
~~
Obtain and review Procedure 8.1 Procedure Performance Determine the applicable procedure subsection to perform as follows:
(J IF reactor power is LESS THAN 25%, THEN perform Subsection 8.2.
(J IF reactor power is GREATER THAN OR EQUAL TO 25%, AND the MONICORE programs are operable, THEN perform Subsection 8.3.
(J IF reactor power is GREATER THAN OR EQUAL TO 25%, AND the MONICORE programs are not operable, THEN have Reactor Enaineerina oerform Subsection 8.4.
8.3.1 IF core power has changed GREATER THAN 2%, OR the control rod pattern has changed since the last core performance program was executed, THEN demand an Official 3D Program.
Candidate obtains and reviews a current CODY of ST-5D I SAT / UNSAT Candidate selects subsection 8.3 Candidate demands Official 3D at 3D keyboard by selecting:
Option 4, Run Official 3D Tab to Execute Select 2 on the number Dad SAT / UNSAT SAT / UNSAT Page 4 of 7
(
S/RO/NLO STEP STANDARD 8.3.2 Determine APRM DR from the higher of the following values:
Largest MFLPD x 100 Percent core thermal power 8.3.3 [ITS] Adjust APRMs per Subsection 8.5.
8.5.1 Record initial APRM readings in Table I.
8.5.2 Record DR in Table 1.
8.5.3 [ITS] Identify any APRM(s) requiring adjustment in Table I.
APRM shall be adjusted to indicate within *2%
Candidate selects Percent Core Thermal Power with a value of -95%.
Candidate records values from Official 3D Candidate records value selected in 8.3.2 Candidate identifies D APRM as requiring adjustment.
ASK TITL EVALUATION I COMMENT SAT / UNSAT SAT / UNSAT SAT I UNSAT SAT / UNSAT
- 4.
EVALUATOR The Shift Manager desires that the APRMs be bypassed for adjustments.
- 5.
SAT / UNSAT
- 6.
- 7.
omitted Der SM.
A. Bypass the APRM channel requiring calibration Der Section E of OP-16.
Obtain and review OP-16 Select proper procedure section E. 16.1 Place ApRM BYP switch in (*).
- 8.
SAT / UNSAT SAT / UNSAT SAT I UNSAT SAT / UNSAT N/A Candidate obtains and review OP-16 noting any cautions that mav be amlicable Candidate selects section E. 16 At 09-5 panel, candidate selects B division joystick to n
- 9.
- 10.
~~
- 11.
- 12.
- 13.
of the DR.
8.5.4 IF APRM adjustment is required, THEN perform the following for each APRM requiring adjustment:
NOTE: Bypassing APRM may be I u.
I
-~
~~
E. 16.2 Verify APRM (*) is bypassed using one or both of the following:
APRM (*) BYPASS indicating light is on APRM (*)
EPIC alarm indicates bypassed At 09-5 panel, candidate observes white bypass lamp for APRM D.
OR Candidate notes EPIC alarm typer indicates selected APRM bypass is ON SAT / UNSAT Page 5 of 7
SlROlNLO NEW
- 17.
- 18.
- 19.
- 20.
- 21.
4SK TITLE: ST-SD STEP NOTE: Clockwise turn raises meter reading; counterclockwise turn lowers meter reading.
D. [ITS] Turn gain adjustment control (R16) on LPRM card 2-31 to obtain a meter readina within k2% of DR.
E. Unbypass APRM per Section E of Candidate obtains OP-I 6 and selects section E. 17 E. 17.1 Verify the following lights for APRM (*) are off at panel 09-14:
OP-I 6.
INOP UPSCL NEUT TRIP UPSCL THERM TRIP E.17.2 Place APRM BYP switch for APRM (*) in center position.
- 14.
- 15.
- 16.
E.16.3 Verify the other two APRM channels associated with the same APRM BYP switch are in service using one or both of the following:
APRM BYPASS indicating lights are off for the other two APRMs No EPIC bypassed alarms for the other two A P R M S ST-5D, 8.5.4 continued:
B. Ensure METER FUNCTION switch is set to AVERAGE.
C. Ensure APRM MODE switch is in the OPERATE position.
~
STANDARD Candidate notes the absence of the same indications for the remaining APRMs in that RPS division (B and F).
At panel 09-14, candidate selects D APRM and confirms Meter Function switch is in average.
~~
At panel 09-14, candidate selects D APRM and confirms Mode switch is in operate.
- ~-
At panel 09-14, candidate inserts small screwdriver into upper left simulated rheostat for the D APRM.
Candidate turns clockwise to raise indication to -95%.
EVALllATOR In the simulator, 2-31 card can be identified but the photos do not support reading R-16 N/A Candidate obtains procedure.
~~
At top of paneT09-14, candidate identifies lamps for the D APRM.
At panel 09-5, candidate selects B division APRM joystick to center position.
EVALUATION I COMMENT SAT / UNSAT SAT / UNSAT SAT / UNSAT SAT / UNSAT SAT / UNSAT SAT I UNSAT SAT / UNSAT SAT / UNSAT Page 6 of 7
S/RO/NLO NEW STANDARD At 09-5 panel, candidate observes bypass lamp extinguished OR Candidate notes alarm typer indicates APRM bypass is OFF EVALUATION I COMMENT SAT / UNSAT
- 22.
- 23.
- 24.
Candidates notes above indications for the B and F APRMs.
STEP E.17.3 Verifi APRM (*) is returned to service using one or both of the APRM (*) BYPASS indicating light is Off No EPIC bwassed alarm for APRM (*)
E. 17.4 Verify all three APRM channels associated with the same APRM BYP switch are in service using one or both of the following:
APRM BYPASS indicating lights are off for the three APRMs No EPIC bypassed alarms for the three A P R M S 8.5.5 Record final APRM readings for adiusted APRMs in Table 1.
fo 110 wing:
SAT / UNSAT Candidate record final reading.
SAT / UNSAT I
FVAl IJATOR: Terminate the task at this point.
Page 7 of 7
L-ENTERGY NUCLEAR OPERATIONS, INC.
OPERATIONS SURVEILLANCE TEST PROCEDURE JAMES A. FITZPATRICK NUCLEAR POWER PLANT APRM CALIBRATION ST-5D REVISION 2 EFFECTIVE DATE:
/2t IO* rn FIRST ISSUE a FULL RESTISION 0 LIMITED REVISION I
CONTINUOUS USE TSR TECHNICAL
APRM CALIBRATION ST-5D REVISION
SUMMARY
SHEET REV. NO.
CHANGE AND REASON FOR CHANGE 2
Revised Step 8.5.5 to require final APRM readings to be recorded only for APRMs that were adjusted. (PCR #1 dated 8 / 9 / 0 0, EC #1 dated 9 / 5 / 0 0 )
Updated subsection 1.1, Frequency and revised section 1.2 in accordance with improved Technical Specifications ( I T S ).
Added subsection 1.3 Technical Requirements Manual (TRM) and applicable reference.
Revised Steps 8.2.l.c, 8.2.3.C, 8.3.3, 8.4.4 to "Adjust APRM(s) per subsection 8.5". Revised steps 8.5.3 and 8.5.4.D, which adjust APRM(s), to obtain a meter reading within -12% of desired reading (DR).
Marked Step 6. 2. 7 as CTS. The step implies that APRM can be adjusted to greater than 2% above desired reading, which is not allowed per ITS SR 3.3.1.1.2.
Added note to step 8.5.5 to state tech spec acceptance criteria and updated section 10.0, Acceptance Criteria.
Rev. No. 2 Page 2 of 24
APRM CALIBRATION ST-5D TABLE OF CONTENTS SECTION PAGE 4
1.0 REQUIREMENTS 5
2.0 PURPOSE........................
5 6
6 7
3.0 REFERENCES
4.0 PREREQUISITES...................,.
5.0 TEST EQUIPMENT, SPECIAL TOOLS, AND UTERIALS 6.0 PRECAUTIONS AND LIMITATIONS..............
9 7.0 GENERAL TEST METHODS 8.0 PROCEDURE.......................
10 8.1 Procedure Performance.................
1 0 8.2 APRM Calibration Less Than 25% of Rated Power.....
11 8.3 APRM Calibration Greater Than or Equal to 25%.....
15 8.4 Manual Calculation by Reactor Analyst Group When Greater Than or Equal to 25%...........
16 8.5 APRM Gain Adjustments.................
17 10.0 ACCEPTANCE CRITERIA..................
19 11.0 ACCEPTANCE VERIFICATION................
20 1 2. 0 ATTACHMENTS...... -... -...........
23
- 1. TEST SIGNOFF LOG 24 Rev. No. 2 Page 3 of 24
ST-5D APRM CALIBRATION 1.0 REQUIREMENTS 1.1 Frequency 1 CTS I Once daily while in the Run Mode CITSI NOTE :
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after THERMAL POWER 225% RTP.
[ITS]
Once every 7 days 1.2 Technical Specifications 1.2.1 Surveillance Requirements
[CTSI 4.1.A 4.1.B
[ITS]
SR 3.3.1.1.2 (Table 3.3.1.1-1, Functions 2.b and 2.c)
SR 3.2.4.2 1.2.2 Limiting Conditions for Operation
[CTSI None
[ITS]
LCO 3.2.4 Leo 3.3.1.1 E ITS 1 1.3 Technical Requirements Manual (TRM) 1.3.1 TRO 3.3.B 1.3.2 TRS 3.3.B.2 (Table T3.3.B-1, Function 1.b) 1.4 Other None 1.5 Commitments 1.5.1 LER 90-003, requires implementation of alternate method of calculating core power below 20% of rated.
Rev. No. 2 Page 4 of 24
'v' APRM CALIBRATION ST-5D 1.6 Expectations 1.6.1 OER 940119, Compare heat balance results to calculated power levels to ensure no reactor overpower due to feed flow input errors.
1.6.2 DER-98-02032, ACT-98-35526, Revised procedure f o r APRM gain adjustment to improve human factors.
1.6.3 JAF-SE-00-028, Added precaution to describe required compensatory actions for a failed or unreliable feedwater temperature input to the 3D Monicore.
2.0 PURPOSE To calibrate Average Power Range Monitor (APRM) System.
3.0 REFERENCES
3.1 Performance References 3.1.1 OP-16, Neutron Monitoring 3.1.2 RAP-7.3.3, Core Thermal Power Evaluation 3.2 Developmental References RAP-7.4.5, APRM Calibration Rev. No. 2 Page 5 of 24
APRM CALIBRATION ST-5D NOTE: Sections 4 and 5 may be performed in any order or concurrently.
4.0 PREREQUISITES 4.1 SM has granted permission to perform this test.
Init 4 2 4. 2 Revision Number of this Working Copy is the same as the revision number listed in the Master Copy of the Index of Operations Surveillance Test Procedures.
Test personnel have read this procedure and are thoroughly familiar with its contents.
4.3 4.4 Start of test recorded.
T C O < L (
//G Jhro c:\\C.
2 d
Da&/Time 4.5 Start of test recorded in NCO Log Book.
4.6 No control rod movement or recirculation flow changes are in progress.
5.0 TEST EQUIPMENT, SPECIAL TOOLS, AND MATERIALS 5.1 Test Equipment None 5.2 Special Tools A very small flathead screwdriver 5.3 Materials None Rev. NO. 2 Page 6 of 24
L-V APRM CALIBRATION ST-5D 6.0 PRECAUTIONS AND LIMITATIONS 6.1 Precautions IEXPl.6.3 If one of the four feedwater temperature inputs to the 3D Monicore (02TE-l40A, 02TE-l40B, 02TE-l40C, or 02TE-140D) fails or becomes unreliable, then one of the following compensatory actions is required:
Procedure changes (such as ST-4OD) to require that a substitute value is inserted for the associated EPIC point.
lowest reading operable feedwater temperature indication from EPIC-A-407, 408, 410, or 411. This value shall be adjusted daily before performing ST-5D and ST-5E, and as soon as practicable after changes in reactor power.
The substitute value shall be equal to the Temporary modification to provide an alternate feedwater temperature input to the plant process computer.
modification shall use the redundant temperature element on the same feedwater line as the sole value for that feedwater line. This method is preferred over operator inserted substitute values.
This 6.2 Limitations 6.2.1 Test personnel shall immediately notify the NCO or CRS of any failure to meet acceptance criteria.
6.2.2 Test personnel shall print name, sign initials, and enter date on Attachment 1 before performing Section 8 of this test.
6.2.3 When test personnel complete their assigned portion of this test, they shall enter hours worked on.
6.2.4 Once this test has been started, any additional test personnel shall read this procedure and become thoroughly familiar with its contents before performing any portion of this test.
Rev. No. 2 Page 7 of 24
'v ST-SD APRM CALIBRATION 6.2.5 Multiple working copies of this test may be used provided the following requirements are satisfied:
NOTE: The work site is defined as the location where work is controlled. The location of the work site is at the discretion of the NCO/ SNO.
A. A working copy of this test shall be retained at the work site.
B. The work site working copy shall be the legal record for documenting this test.
C. Data from all steps performed away from the work site, including signatures, initials, and recorded values, is transcribed into the work site working copy following completion of the test.
6.2.6 If the ratio of MFLPD/FRP is greater than 1.0, then compliance with Tech Specs is accomplished by making the APRM read greater than or equal to MFLPD instead of lowering APRM trip setpoints.
[CTSI 6. 2. 7 If an APRM gain adjustment results in nuisance rod block alarms, then the preferred action is to request a rod pattern adjustment from the reactor engineer. As an alternate, the APRM gain may be adjusted with SM permission to bring the alarm in solid. This option should be minimized to prevent masking the alarm.
6.2.8 Conditional (IF, THEN) steps in this test may be marked aNA" if not applicable.
6.2.9 Steps in this test marked NRfl are not required to be initialed.
Rev. No. 2 Page 8 of 2 4
. ~. __ -..
ST-5D APRM CALIBRATION 7.0 GENERAL TEST METHODS 7.1 This test consists of five subsections which determines the method used for calibrating the Average Power Range Monitor (APRM) System.
7.2 This test contains the following subsections:
7.2.1 Determine procedure subsection to perform per the criteria provided in Subsection 8.1.
7.2.2 Determine APRM desired reading (DR).
7.2.3 Calibrate APRMs per Subsection 8.5.
Rev. No. 2
L APRM CALIBRATION ST-5D 8.0 PROCEDURE Init 8.1 P r o c e d u r e P e r f o r m a n c e Determine the applicable procedure subsection to perform as follows:
(-)
IF reactor power is LESS THAN 25%,
THEN perform Subsection 8.2.
IF reactor power is GREATER THAN OR EQUAL TO 25%,
AND the MONICORE programs are operable, THEN perform Subsection 8.3.
IF reactor power is GREATER THAN OR EQUAL TO 25%,
AND the MONICORE programs are not operable, THEN have Reactor Engineering perform Subsection 8.4.
(-1
(-1 Rev. No. 2 Page 10 of 24
APRM CALIBRATION ST-5D c-UCOMl -5.1 8.2 APRM Calibration Less Than 25% of Rated Power NOTE 1: APRM calibration per OP-65 is performed per Steps 8.2.1 and 8.2.2.
NOTE 2:
Core Thermal Power and Flow Log will abort if feedwater flow rate is too low.
8.2.1 IF both of the following conditions exist:
Reactor pressure GREATER THAN 970 psig BPV-1 near full open AND all other bypass valves full closed
(-1 THEN perform the following:
A. Demand Core Power and Flow Log.
B. Determine APRM DR as follows:
(-1 IF result of Core Power and Flow Log program is BETWEEN 9 and 14% power, THEN DR equals the power level determined per Step 8.2.1.A.
(-1 IF result of Core Power and Flow Log program is not BETWEEN 9 and 14% power, THEN DR equals 10% power.
Init
(-1 IF Core Power and Flow Log aborted, THEN DR equals 10% power.
DR =
C. [CTS]
Adjust APRMs to read GREATER THAN OR EQUAL TO DR per Subsection 8.5.
CITSl Adjust APRMs per Subsection 8.5.
NR L-Rev. No. 2 Page 11 of 24
APRM CALIBRATION ST-5D Init UEXPl. 6.1 8.2.2 IF both of the following conditions exist:
Reactor pressure GREATER THAN 970 psig
(-1 BPV-1 full open
(-1 BPV-2 near full open
(-1 All other bypass valves full closed
(-1 THEN perform the following:
A. Demand Core Power And Flow Log.
B. IF Core Power and Flow Log program aborts due to low feedwater flow rate, THEN issue a PID for I&C Department to investigate and perform necessary repairs.
NOTE: While I&C is troubleshooting, APRMs may be calibrated per Steps 8.2.2.C through 8.2.2.E.
C. Determine APRM DR as follows:
( - ) IF result of Core Power and Flow Log program is BETWEEN 17 and 22% power, THEN DR equals the power level determined per Step 8.2.2.A.
(-1 IF result of Core Power and Flow Log program is not BETWEEN 17 and 22% power, THEN DR equals 17% power.
(-1 IF Core Power and Flow Log aborted, THEN DR equals 1 7 % power.
DR =
D. IF Core Power And Flow Log result is not BETWgEN 17 and 22% power, THEN investigate cause of discrepancy before raising power above 20% of rated.
Rev. No. 2 Page 12 of 24
L-.
APRM CALIBRATION ST.- 5D Init E.
[CTS]
Adjust APRMs to read GREATER THAN OR
~~
EQUAL TO DR per Subsection 8.5.
[ITS]
Adjust APRMs per Subsection 8.5.
8.2.3 I F both of the following conditions exist:
Reactor pressure GRgATER THAN 9 7 0 psig Conditions other than specified in Steps 8.2.1 and 8.2.2 exists (such as a different combination of bypass valves open, or main generator in service)
(-1 THEN perform the following:
A. Demand Core Power and Flow Log.
B. Determine APRM DR as follows:
- 1. IF both of the following conditions exist:
0 BPV-1 full open AND BPV-2 is not near full open THEN determine DR as follows:
NR
(-)
IF result of Core Power and Flow Log program is BETWEZN 10 and 17%
- power, THEN DR equals the power level determined per Step 8.2.3.A.
(-1 IF result of Core Power and Flow Log program is not BETWEEN 10 and 17% power, THEN DR equals 15% power.
( - ) I F Core Power and Flow Log aborted, THEN DR equals 15% power.
DR =
(Step 8.2.3.B continued on next page)
Rev. No. 2 Page 13 of 24
APRM CALIBRATION ST-SD 8.2.3.B (Cont)
Init
- 2. IF all of the following conditions exist:
BPV-1 full open
(-1 BPV-2 full open
(-1 BPV-3 is not near full open
(-1 THEN determine DR as follows:
(-1 IF result of Core Power and Flow Log program is BETWEEN 17 and 24%
- power, THEN DR equals the power level determined per Step 8.2.3.A.
(-1 IF result of Core Power and Flow Log program is not BETWEEN 17 and 24%
- power, THEN DR equals 22% power.
( - ) IF Core Power and Flow Log aborted, THEN DR equals 22% power.
DR =
- 3. IF the main generator is in service, THEN DR is the power level determined per Step 8.2.3.A.
DR =
C. [CTS]
Adjust APRMs to read GREATER THAN OR EQUAL TO DR per Subsection 8. 5.
[ITS]
Adjust APRMs per Subsection 8.5.
NR Rev. No. 2 Page 14 of 2 4
L-
~.
APRM CALIBRATION ST-5D 8.3 APRM Calibration Greater Than or Equal to 25%
Init 8.3.1 IF core power has changed GREATER THAN 2%,
OR the control rod pattern has changed since the last core performance program was executed, THEN demand an Official 3D Program.
8.3.2 Determine APRM DR from the higher of the following values :
Largest MFLPD x 100 x 100 =
Largest MFLPD Percent core thermal power Thermal power =
B
(-1 DR =
8.3.3
[CTSI Adjust APRMs to read GRgATER THAN OR EQUAL TO DR per Subsection 8.5.
[ITS]
Adjust APRMs per Subsection 8.5.
NR
'L Rev. No. 2 Page 15 of 24
8.4 Manual Calculation by Reactor Analyst Group When Greater Than or Equal to 25%
8.4.1 Calculate core thermal power per RAP-7.3.3.
RE 8.4.2 Use the Manual Monitor Menu to run an Official 3D Program.
. RE 8.4.3 Determine the APRM DR from the higher of the following values:
Largest MFLPD x 100 x 100 =
(-1 Largest MFLPD FRP x 100 x 100 =
(-1 FRP DR =
RE 8.4.4 CTS 1 Adjust APRMs to read GREATER THAN OR EQUAL TO DR per Subsection 8.5.
E ITS1 Adjust APRMs per Subsection 8.5.
Rev. No. 2 NR Page 16 of 24
APRM CALIBRATION ST-5D UEXPl. 6.2 8.5 APRM G a i n Adjustments Init 8.5.1 8.5.2 Record DR in Table 1.
Record initial APRM readings in Table 1.
8.5.3
[CTSI Identify any APRM(s) requiring adjustment in Table 1. APRM shall be adjusted to indicate GRgATER TKAN OR EQUAL TO the DR.
[ITSI Identify any APRM ( s ) requiring adjustment in Table 1. APRM shall be adjusted to indicate within +2% of the DR.
8.5.4 IF APRM adjustment is required, THEN perform the following for each APRM requiring adjustment:
NOTE:
A. Bypass the APRM channel requiring Bypassing APRM may be omitted per SM.
calibration per Section E of OP-16.
NR Rev. No. 2 B. Ensure METER FUNCTION switch is set to NR AVERAGE.
C. Ensure APRM MODE switch is in the OPERATE NR posit ion.
NOTE:
Clockwise turn raises meter reading; counterclockwise turn lowers meter reading.
D. [CTS]
Turn gain adjustment control (R16) on LPRM card 2-31 to obtain a meter reading GREATER THAN OR EQUAL TO DR.
[ITSI Turn gain adjustment control (R16) on LPRM card 2-31 to obtain a meter reading within
+2% of DR.
NR E. Unbypass APRM per Section E of OP-16.
NR Page 17 of 24
APRM CALIBRATION S T - 5 D I n i t CITSI NOTE :
8. 5. 5 Tech spec acceptance criteria f o r "Final R e a d i n g "
shall be w i t h i n +2% of DR.
R e c o r d f i n a l APRM readings f o r adjusted APRMs i n Table 1.
TABLE 1 APRM GAIN ADJUSTMENTS DESIRED READING R e v. No. 2 Page 18 of 24
~
_.I_-
APRM CALIBRATION ST-5D Init 9.0 RETURN TO NORMAL 9.1 System Restoration 9.1.1 Operable APRMs are unbypassed.
9.1.2 Step 9.1.1 verified by Licensed Operator.
Signature/Date 9.2 Review and Signoff 9.2.1 Test completed.
Date /Time 9.2.2 Calculations performed in the following steps have been independently verified:
8. 3. 2 8.4.3 Independent verification
/
SignaturejDate 9.2.3 Test personnel have recorded hours worked on.
9.2.4 Man-Hours totalled and recorded on.
9.2.5 Completion of test recorded in NCO Log Book.
10.0 ACCEPTANCE CRITERIA ICTSI Operable APRMs are reading greater than or equal to DR.
[ITS1 Operable APRMs are reading within +2% of DR.
Rev. NO. 2 Page 13 of 24
APRM CALIBRATION ST-5D 11.0 ACCEPTANCE VERIFICATION 11.1 NCO/SNO Review 11.1.1 11 -1.2 11.1.3 11.1.4 11.1.5 11.1.6 11.1.7 Verify required data has been recorded and is within required tolerances.
Verify required initials and signatures have been entered.
Review test to determine if test acceptance criteria has been satisfied.
Check one of the following as appropriate for test results:
(-1
(-1 Acceptance criteria satisfied, corrective
(-)
Acceptance criteria not satisfied.
IF acceptance criteria is satisfied AND corrective action is required, THEN perform the following:
A. Describe in Subsection 11.3, Remarks.
Acceptance criteria satisfied, no corrective action required.
action required.
B. Initiate a PID and record PID number.
PID Number IF acceptance criteria is not satisfied, THEN perform the following:
A. Immediately notify SM.
B. Initiate a PID and record PID number.
PID Number Sign and record date and time.
Da t e/Time SNO or NCO Rev. No. 2 Page 20 of 24
L i,
APRM CALIBRATION ST-5D 11.2 Management SRO Review 11.2.1 11.2.2 11.2.3 11.2.4 11.2.5 11.2.6 11.2.7 11.2.8 11.2.9 Rev. No. 2 Verify current revision of surveillance test procedure was used.
Verify surveillance test was completed within required test frequency.
Verify data tables and attachments have been properly completed.
Verify required data has been recorded and is within required tolerances.
Verify required initials and signatures have been entered.
Review test to determine if test results satisfy acceptance criteria.
Check one of the following as appropriate for test results :
(-1 Acceptance criteria satisfied.
(-1 Acceptance criteria not satisfied.
IF acceptance criteria is not satisfied, THEN perform the following:
A. Immediately notify Operations Manager or alternate.
B. Record name of person notified.
Person Notified C. Initiate required corrective and compensatory actions.
Sign and record date and time.
Management SRO Date /T ime Page 21 of 24
I i-.
APRM CALIBRATION ST-5D 11.3 Remarks Rev. No. 2 Page 22 of 24
APRM CALIBRATION ST-5D 12. 0 ATTACHMENTS
- 1. TEST SIGNOFF LOG R e v. No. 2 Page 2 3 of 24
'V-ST-5D APRM CALIBRATION ATTACHMENT 1 Page 1 of 1 TEST SIGNOFF LOG Total Man-Hours Rev. No. 2 Page 24 of 24
- m lclcl
=Entergy James A. FitzPatrick Nuclear Power Plant Nuelear Northeast OPERATIONS TRAINING PROGRAMS JOB PERFORMANCE MEASURE S/RO NEW TASK TITLE: OP-63 WEEKLY ALARM TEST APPL. TO JPM NUMBER REV: 0 DATE: 5/25/03 NRC WA SYSTEM NUMBER: 7 1 16 7 9 JAF TASK NUMBER:
JAF QUAL STANDARD NUMBER:
ESTIMATED SUBMITTED:
OPERATION REVIEW:
APPROVED:
CANDIDATE NAME:
S.S. NUMBER:
JPM Completion:
( ) Simulated
( X ) Performed L-Location:
( ) Plant
( X ) Simulator DATE PERFORMED:
PERFORMANCE EVALUATION:
( ) Satisfactory
( ) Unsatisfactory TIME TO COMPLETE: -
Minutes N ~ N ~ N N N N N N U U N N N N N N U N u N N N N ~ N N U N N U U N N U ~ N N N N N N m N N U - N ~ N N N U N N U N N N N U U ~ N U N N N - N N N N N N N N U N COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)
EVALUATOR:
S IG NATU RE/PR I NTED CANDIDATE REVIEW:
SIGNATURE REVIEWED BY:
DOC. COMPLETE:
PROGRAM ADMINISTER
'c Page I of 5
\\S/RO NEW TASK TITLE: OP-63 WEEKLY ALARM TEST APPL. TO JPM NUMBER Current Update: 5/25/03 By: RWD Date Int.
Outstanding Items:
Technical Review Questions and Answers Procedural Change Required Comments:
Simulator validated 5/25/03. Any IC Previous Revision Dates:
Additional Information Validation None Page 2
- of 5
~ - -.,c
~ U r n pttw-ummnlrbr iekMbcii REQUIRED TASK INFORMATION
-S/RO NEW TASK TITLE: OP-63 WEEKLY ALARM TEST APPL. TO JPM NUMBER
- 1.
II.
111.
IV.
L V.
VI.
SAFETY CONSIDERATIONS A.
Ensure proper safety equipment and safety procedures are observed.
REFERENCES A.
OP-63, INTRA-PLANT COMMUNICATIONS SYSTEM, Rev. 6 TOOLS AND EQUIPMENT A.
None SET UP REQUIREMENTS A.
B.
EVALUATOR NOTES A.
If performing JPM in the plant, inform the candidate that the conditions of each step need only be properly identified and mt actually performed.
The candidate should, at a minimum, identify the change in equipment status light indication when equipment operation is simulated.
B.
TASK CONDITIONS A.
Candidate will be ordered to conduct a routine weekly test of the plant communication system.
- - CRITICAL STEP c
Page 3 of 5
(
S/RO/NLO TASK TITLE:
VII.
INITIATING CUE STEP STANDARD Obtain procedure E.3.1 Make the following announcement over the Gai-Tronics:
"Attention, Attention, the following is a test of the plant alarms. Attention, Attention, the following is a test of the plant alarms."
Candidate obtains OP-63 and selects section E.3 Candidate selects any Gai-Tronics push to talk handset and makes the announcement.
E.3.2 Announce:
and makes the announcement.
Candidate selects any Gai-Tronics push to talk handset "The first alarm is the Station Alarm. The first alarm is the Station Alarm."
Perform OP-63 Weekly Alarm Testing EVALUATION I COMMENT SAT / UNSAT SAT / UNSAT SAT / UNSAT
- 1.
- 2.
seconds.
E.3.4 Silence the alarm by depressing the OFF oushbutton.
E.3.5 Announce:
"The next alarm is the Evacuation Alarm. The next alarm is the Evacuation Alarm."
- 3.
- 4
- Candidate depresses the OFF pushbutton Candidate selects any Gai-Tronics push to talk handset and makes the announcement.
- 5.
- 6.
('
SAT / UNSAT Page 4 of 5
S/RO/NLO 4SK TITLE:
STEP STANDARD E.3.6 Depress EVAC pushbutton and allow the alarm to sound for approximately I O seconds.
Silence the alarm by depressing the OFF oushbutton.
E.3.8 Announce:
Candidate depress EVAC pushbutton and allow audible alarm for approximately 10 seconds
- 7.
- 8.
E.3.7 Candidate depresses the OFF pushbutton Candidate selects any Gai-Tronics push to talk handset and makes the announcement.
- 9.
The next alarm is the Fire Alarm. The next alarm is the Fire Alarm I
- 0.
E.3.9 Candidate depress FIRE pushbutton and allow audible Depress pushbutton and alarm for approximately I O seconds the alarm to sound for approximately 10 seconds.
Silence the alarm by depressing the OFF oushbutton.
E.3.11 Announce:
- 11.
E.3.10 Candidate depresses the OFF pushbutton Candidate selects any Gai-Tronics push to talk handset and makes the announcement.
- 12.
This completes the test of the EVALUATION I COMMENT SAT / UNSAT SAT / UNSAT SAT / UNSAT SAT / UNSAT SAT / UNSAT SAT / UNSAT FVAl 1 IATOR: Terminate the task at this point.
1 i Page 5 of 5