Text

Draft - Section a Operating
	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)
	v • d • e

"Entwgy Nuclear Northeast James A. FitzPatrick Nuclear Power Plant OPERATIONS TRAINING PROGRAMS SRO NEW TASK TITLE: CANAL DISCHARGE APPROVAL APPL. TO JPM NUMBER REV: 0 DATE: 5/23/03 NRC K/A SYSTEM NUMBER: 233 7 113.1 JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 2 0Minutes SUBMITTED:

APPROVED:

1 w OPERATION REVIEW:

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 REVIEW:

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 P t K P U K W N b r rnhkibii; REQUIRED TASK INFORMATION NEW TASK TITLE: CANAL DISCHARGE APPROVAL APPL. TO JPM NUMBER

1. SAFETY CONSIDERATIONS A. Ensure proper safety equipment and safety procedures are observed.

II. REFERENCES A. OP-49, LIQUID RADIOACTIVE WASTE SYSTEM, Rev. 51 111. TOOLS AND EQUIPMENT A. Calculator IV. SET UP REQUIREMENTS A. Simulator in any operating configuration with tempering gate full closed

8. 17RM-350 data sheet containing background and K-factor is posted at 09-1 1 C. Operator Aid 446 available in Shift Manager Office L.

D. Partially completed Canal Discharge Worksheet (OP-49 Attachment 5).

E. Confirm or correct calculations for current revisions of Op Aid 446 and Liquid Process Monitor Cal Data 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.

6. The candidate should, at a minimum, identify the change in equipment status light indication when equipment operation is simulated.

VI. TASK CONDITIONS A. Candidate is presented with a partially completed Canal Discharge Worksheet.

B. Candidate completes worksheet and sets 17RM-350for canal discharge.

CRITICAL STEP L-Page 3 of 5

S/RO/NLO NEW TASK TITLE: CANAL DISCHARGE APPROVAL VII. INITIATING CUE You are the Shift Manager. Waste Sample Tank A has been in recycle for the last 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . Complete this Canal Discharge Worksheet and set the radiation monitor in preparation for discharging the sample tank.

EVALUILTOR Hand partially completed Canal Discharge Worksheet to candidate.

STEP STANDARD EVALUATION I COMMENT I. Select procedure Candidate selects OP-49, Section E.23 SAT / UNSAT

2. 7. Liquid rad monitor (17RM-350) Candidate records 43 from Liquid Process Monitor Cal SAT / UNSAT background cps Data posted at 09-11 panel

3. 8. Liquid rad monitor (17RM-350) K- Candidate records 2.09E-7 from Liquid Process Monitor SAT / UNSAT factor pCi/mllcps Cal Data posted at 09-11 panel 11 If

4. I 9. Tempering gate/flow %

I I Candidate obtains EPIC value of 0% (EPIC-A-3547)

I 1

I SAT I UNSAT 11 5. 1 10. Calculate Canal Flow Rate (CFR): 1 396,000 I SAT / UNSAT

6. 11. Calculate Canal Dilution Factor 5.05E-5 SAT / UNSAT (CDF):

7. 12. Calculate FL: 5.05E-3 SAT I UNSAT~- -

-~ ~ ~~- _ _ _ ~ ~ ~

a. 13. Calculate Background Correction 5.6E-6 SAT / UNSAT Activitv (BCA) in uCi/ml:

g. 14. Calculate HVHi setpoint in pCVrnl: 3.8E-2 SAT / UNSAT

I 0. 15. Calculate Hi setpoint in pCVml: 1.9E-2 SAT / UNSAT

11. 16. Obtain 17RM-350 potentiometer 8.8 turns SAT I UNSAT setting for Hi-Hi setpoint from OPAID 446.

12. 17. Obtain 17RM-350 potentiometer 8.4 turns SAT / UNSAT settina for Hi setDoint from OPAID 446.

Page 4 of 5

?

STEP STANDARD EVALUATION / COMMENT

13. 18. Enter potentiometer settings for Hi F~Al SAT / UNSAT and Hi-Hi setpoints on Discharge I Permit Section B and attach this Indicate that this activity is complete worksheet to the discharge permit. ti Adjust 17RM-350 setpoints At panel 09-11, candidate unlocks HI and HI-HI i

14.

Potentiometers and adjusts to 8.4 and 8.8 turns rewectivelv. Candidate re-locks the ootentiometers.

SAT / UNSAT r

Page 5 of 5

LA&

1.

Number of running circulating water pumps (36P-lA/B/C) d 0

5

2. N m e r of rurming service water pLlIll2s (46P-lA/B/C) 2

3. Tank Discnarge Flow Rate (maximum) TDFR 2c GPT-

-4

4. Tank Activity (ACT) 2 - S X pCi/ml (from c i i s c h a r g e perziz!

NOTE 1: Items 7 and 8 are obtained at panel 09-14 NOTE 2: Background should be maintained LESS THAN 1000 c-p- s .

It is recommended that the detector caniscer be ri.ished to levels below this prior to discharge.

7. Liquid rad monitor (17RM-350) background 43 n cps

8. Liquid rad monitor

5. Tempering gate/flow 0 %

(ZPIC-A-3547)

CALCULATIONS

10. Calculate Canal Flow Rate (CFR):

CPR = ( e l x 120,000! i ($2 x 18,000! = T54cP-,!-)3Qgpm

/

I - (#9 + 100)

11. Calculate Canal Dilution Factor -(CDF):

12. Calculate F,:

-3 F, = CDF X DF = #11 X #5 = 5.3SXO

13. Calculate Background Correction Activity (BCA) in pCi/ml:

BCA = (#6 - #7) X #8 = c.,,r,tO

-k pCi /ml L-OP-49 LIQUID RADIOACTIVE Rev. No. 51 WASTE SYSTEM Page ATTACHMENT 5 214 of 216 -

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)

?rint/Sign/Date Independent Verification 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

Liquid Radwaste Effluent Monitor Sample Activity vrs. Alarm Pot Setting 10 9

8 7

w 6 C

ea, h n- 5 51 E

L (II z

I.OE-7 I.OE-6 1.OE-5 'l.OE-4 1.OE-3 1.OE-2 1.OE-1 Sample Activity (uCilml)

(XI NOTE: ---------___--_--_

>> INCREASING ACTIVITY--

Cal Date: 5/13/03 I- - - - HIGH ALARM POT A HIGH-HIGHALARM POT - ----I 5/? )I3

Page 1 of 1 TO CALCULATE ACTIVITY:

MONITOR ID ID # CAL DATE BACKGROUND K FACTOR CPS uCl/ml CPS RADWASTE LIQUID 17RM-350 5/,3 / 6 3 73 aJ?qE-7 NORMAL 17RM-351 SERVICE WATER Y/a9/03 2- 2 . 3 G i5-7 RBCLC 17RM-352 af? 2.3aL5-7 i

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

2. Number of running service water pumps (46P-lA/B/C)

L-

3. Tank Discharge Flow Rate (maximum) TDFR 2 c; q;r,

-u 9

4. Tank Activity (ACT) 3/2 LCi/ml (from discharge p e r z d z !

6. Liquid ra2 moniror (17REI-350) reading 7c C?S (EPIC-A-1209)

NOTE I: 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 caRister be fleshed to levels below this prior to discharge.

7. Liquid rad monitor (17RM-350) backgroun6 cps

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,:

FL = CDF X DF = #11 X # 5 =

- OP-49 LIQUID RADIOACTIVE ATTACXMENT 5 -

Rev. No. 51 WASTE SYSTEM Page 214 of 216

14. Calculate Hi/Hi setpoint in pCi/ml:

Hi/HI = (ACT) $13 2 x F. 2 x $12

15. Calculate Hi setpoint in pCi/ml:

Hi = (ACT) - e4 + #13 4 x Fi 4 x #12

16. Obtain 17W-350 potentiometer OPAID 446.

17. Obtain 1 7 W - 3 5 0 potentiometer setting for Hi setpoia:

from ODAID 446.

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 L- I, rl OP-49 LIQUID RADIOACTIVE ATTACHMENT 5 Rev. No. 51 WASTE SYSTEM Page 215 of 216

Enteqy Nuclear Northeast James A. FitzPatrick Nuclear Power Plant OPERATIONS TRAINING PROGRAMS NCEMEASURE SRO NEW- TASK TITLE: EVALUATE SURVEILLANCE TEST ACCEPTANCE CRITERIA APPL. TO JPM NUMBER 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: 2 0Minutes SUBMITTED: - OPERATION REVIEW:

APPROVED:

CANDIDATE NAME: S.S. NUMBER:

JPM Completion: ( ) Simulated ( )Performed c

Location: ( ) Plant ( )Simulator DATE PERFORMED: TIME TO COMPLETE: -Minutes PERFORMANCE EVALUATION: ( ) Satisfactory ( ) Unsatisfactory EVALUAT0 R:

SIGNATUREIPRINTED 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 -Validation

-Procedural Change Required -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. AP-03.11, OPERABILITY AND REPORTABILITY DETERMINATIONS

9. AP-19.01, SURVEILLANCE TESTING PROGRAM C. ST-01B, MSlV FAST CLOSURE TEST 111. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS L-.

A. Best if conducted in the Control Room or the simulator.

B. 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.

9. The candidate should, at a minimum, identify the change in equipment status light indication when equipment operation is simulated.

VI. TASK CONDITIONS A. Candidate will review a completed ST-01B Surveillance Test containing test failure data that was nor recorded by the performer or SNO 9.

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.

~~ ~ ~

STEP STANDARD EVALUATION/ COMMENT

1. 11.2.1 Verify data is within required Candidate review all data recorded in Surveillance Test. SAT / UNSAT tolerances.

Candidate may determine that step 8.6.3 does not meet acceptance criteria.

2. 11.2.2 Verify data attachments, such This step is not applicable to this test. SAT I UNSAT as recorder printouts and calibration sheets are included as required.

3. 11.2.3 Verify required initials and Candidate review all initiakignature blocks for SAT / UNSAT signatures have been entered. completion

4. 11.2.4 Review test to determine if test Candidate will recognize that step 8.6.3 does not meet SAT / UNSAT results satisfy acceptance criteria: acceptance criteria and therefore check the (J Satisfactory Unsatisfactory box (J Satisfactory with corrective actions 1 Unsatisfactorv

5. 11.2.5 IF Level 1 acceptance criteria is Candidate will make the required notification SAT / UNSAT not satisfied, THEN immediately notify Operations Manager or alternate. EVALUATOR Record name of person notified. Receive and acknowledge the notification

6. 1I.2.6 Initiate required corrective and Candidate will indicate the need to complete a Tech SAT / UNSAT compensatory actions. Spec review, Condition Report and PID and check the (J Not required Required box.

(J Required EVALUATOR ReDort to candidate that all are in progress.

Page 4 of 5

< i S/RO/NLO STEP STANDARD EVALUATION I COMMENT 1 II.2.7Sign and record date and time. Candidate will sign, date and time the surveillance test SAT / UNSAT 7.

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 DATE JCZ

~ESPON$IBLE PR EFFECTIVE DATE:

FIRST ISSUE FULL REVISION 0 LIMITED REVISION 0

CONTINUOUS USE *

TSR

TECHNICAL *

3

MAIN TURBINE BYPASS VALVE CYCLE 'i'ES'Y '.

S T - - L &,,

7 TABLE OF CONTENTS SECTION 1.0 REQUIREMENTS . . . . . . . . . . . . . . . . . . . . .

2.0 PURPOSE . . . . . . . . . . . . . . . . . . . . . . . .

3.0 REFERENCES

. . . . . . . . . . . . . . . . . . . . . . 1 4.0 PREREQUISITES . . . . . . . . . . . . . . . . . . . . .

5.0 TEST EQUIPMENT, SPECIAL TOOLS, AND MATERIALS . . . . .

6.0 PRECAUTIONS AND LIMITATIONS . . . . . . . . . . . . . . b 7.0 GENERAL TEST METHODS . . . . . . . . . . . . . . . . . 7 8.0 PROCEDURE . . . . . . . . . . . . . . . . . . . . . . . E 8.1 Main Turbine Bypass Valve Testing While Shutdown in Cold Condition . . . . . . . . . . . . . . . . . . . . &

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

MAIN TURBINE BYPASS VALVE CYCLE TEST S I - - ?.-&k u - -?

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 . Required prerequisites are established in OP-9 Section D.2 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 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.

4.4 EHC Section (Panel 0 9 - 5 ) Lamp Test has been completed per Subsection G . 2 of OP-9.

4.5 Start of test recorded.

Date/ Time 4.6 Start of test recorded in NCC Log Book.

4.7 Reactor is in Mode 4.

5.0 TEST EQUIPMENT, SPECIAL TOOLS, AND MATERIALS 5.1 Test Equipment None 5.2 Special Tools None 5.3 Materials None Rev. 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.

7.2 This test will be performed in conjunction wlch OF-: Secz:on D.2, Main Turbine Valve Testing While Shutdown ir Cel5 Condition.

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 7of 15

MAIN TURBINE BYPASS VALVE CYCLE TEST S'L'-L l<\

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 t u r b i n e 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. 0

-- Page 9 of 15

MAIN TURBINE BYPASS VALVE CYCLE Y E S T 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.

11.1.2 Verify required initials and signatures nave beeE entered.

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.

11.1.5 IF acceptance criteria is satisfied A N D corrective action is required, THEN perform the following:

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 Date/Time Rev. No. 0 Page 11 of 15

11.3 Remarks Rev. No. 0-- Page 13 of 15

TEST SIGNOFP LOG P R I N T E D NAME INITIALS DATE: DOSE i-:OV2S R ECS I1-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 . No. 3 Page 41 of 4 9

1 DATE: 2 TIME: 3 % PWR 4 MODS:

Other I II 8 CR NO. 1 - -_ _ , . _N U_. _ ^

Y P'IU/WK 10 CONDITION INITIATING LCO: Planned Unplanned

~

11 CONDITION 12 REOUIRED ACTION 13 COMPLETYON TIE ~~ ~

Required by: Completed:

Date:-/-/- Date:-:-/-

Time :

Time : Initials :

Required by: Compieced:

Date:-/-/- Dace: I i-Time :

Time : Initials :

R e q u i r e d by: Compieted:

Date: / /- Date:-!-/-

Time :

Time : initials:

14 COPIPLETE PAGE RECORD NAME/DEPAR"T NOTIFIED IF OTHER THAN OPS REQUIRED TO COMPLETE ACTION :

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 I

20 COMMENTS/CORRECTIVE ACTIONS 4

21 CRS: 1 2 2 SM:

This a Quality Record u

AP-12.08 LCO TRACKING AND SAFETY FUNCTION DETERMINATION PROGRAM ATTACHMENT 1 Rev. No. 3 Page 37 of 4 9

z,rn T ~ A C K T N Gs 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 / In5t i - i /

/ / /

/

This a Quality Record i,

AP-12-08 LCO TRACKING AND SAFETY FUNCTION DETERMINATION PROGRAH ATTACHMENT 1 Rev. No. 3 Page 38 of 4 9

-. Document Description O?EX 2LCS3

?ID/WR/CR/ST D a t e 'TxRe Daze "

me i

i I

1 I

I I

I I I II

-1 I

This a Quality Record L ,

it I AD-12.08 LCO TRACKING AND SAFETY FUNCTION DETERMINATION PROGRAM ATTACHMENT 1 L Rev. N o . 3 Page 2 of 4 9 4

?acre -.-

c-Continuatioz Sheer This Is a Quality Record

\ / 1 AP-12-08 LCO TRACKING AND SAFETY FUNCTION DETERMINATION P R O G M ATTACHMENT 1 Rev. No. 3 Page 4 0of 49

.I

ENTERGY NUCLEAR OPERATIONS, INC.

V 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-Iq-02 FIRST ISSUE 0 FULL REVISION 0 LIMITED REVISION

CONTINUOUS USE f

TSR *

......................... ****************ti*******

TECHNICAL

MSIV FAST CLOSURE TEST (IST) ST-1 B REVISION

SUMMARY

SHEET REV. NO. CHANGE AND REASON FOR CHANGE 23 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) 22 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.

21 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 .

20 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

M S I V FAST CLOSURE TEST (IST) ST-1B c- TABLE OF CONTENTS SECT ION 1.0 REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . . . 4 6

2.0 PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . . .

3.0 REFERENCES

. . . . . . . . . . . . . . . . . . . . . . . . 6 4.0 PREREQUISITES . . . . . . . . . . . . . . . . . . . . . . . 7 5.0 TEST EQUIPMENT, SPECIAL TOOLS, AND MATERIALS . . . . . . . 8 6.0 PRECAUTIONS AND LIMITATIONS . . . . . . . . . . . . . . . . 8 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 . . . . . . . . . . . . . . . . . . . . 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 10.0 ACCEPTANCE CRITERIA . . . . . . . . . . . . . . . . . . . . 18 11.0 ACCEPTANCE VERIFICATION . . . . . . . . . . . . . . . . . . 19 12.0 ATTACHMENTS . . . . . . . . . . . . . . . . . . . . . . . . 23

1. TEST S I G N O F F LOG . . . . . . . . . . . . . . . . . . . 24

--_-- Page 3 of 24 Rev. No. 23

MSIV FAST CLOSURE TEST ( I S T ) ST-1B 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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 Page 4of 24

1.2 Technical Bsmcificati-1.2 .I ~ i l l a a c RsquirarPernt.

0 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 mor 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

MSIV FAST CLOSURE TEST (IST) ST-1B 2.0 PURPOSE To test MSIVs as required by the IST Program.

3.0 REFERENCES

3.1 Performance References None 3.2 Developmental References 3.2.1 ODSO-32, Shutdown Procedure 3.2.2 OP-1, Main Steam System 3.2.3 ASME Section XI 1989 Edition no addenda 3.2.4 Inservice Testing Program For Pumps and Valves, Third Interval 3.2.5 AP-19.05, Pump and Valve Inservice Testing 3.2.6 ESK-7A, 7B 3.2.7 FM-29A 3.2.8 1.67-97 thru 98 3.2.9 1.70-98 thru 110 3.2.10 AP-01.04, Tech Spec Related Requirements, Lists and Tables 3.2.11 NUREG-1482 Guidelines for Inservice Testing at Nuclear Power Plants, Section 3.1.1.1 3.2.12 JD-01-123,GE REM Light Dryer Wet Transfer System Rev. No. 23 Page 6- of 24

MSIV FAST CLOSURE TEST (IST) ST-1B 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.

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.

4.3 Test personnel have read this procedure and are thoroughly familiar with its contents.

4.4 Start of test recorded. Tcoil.( IS

-;hj t i c l o

'Date/Time 4.5 Start of test recorded in SNO Log.

4.6 CCTSl Reactor is shutdown, Reactor Pressure c 5 psig.

[ITS1 Reactor is in Mode 3 , 4 or Mode 5, Reactor Pressure e 5 psig.

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.

4.9 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. k';

Rev. No. 23 Page 7of 24

M S I V FAST CLOSURE T E S T (IST) ST-1B 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 Attachment 1.

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 8of 24

MSIV FAST CLOSURE TEST ( I S T ) 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 S N O .

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

MSIV FAST CLOSURE TEST (IST) ST-1B

--' 7.0 GENERAL TEST METHODS 7.1 This test consists of eight subsections which test MSIVs as required by the IST Program.

7.2 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.

7.3 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:) .

7.4 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

MSIV FAST CLOSURE TEST (IST) ST-1B 8.0 PROCEDURE Init 8.1 MSIV 29AOV-80A Test 8.1.1 Record as-found position of MSIV 29AOV-80A.

ObUJ (pos'ition) 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 Record as-found position of MSIV 29AOV-86A.

closd (position) 8.2.2 Ensure open MSIV 29AOV-86A. 2 8.2.3 Close and time MSIV 29AOV-86A.

Closing time 4- \ secs (IST: 3 to 5 secs)

(TS: 3 to 5 secs) 8.2.4 IF desired to have valve remain closed per Section F of OP-65, THEN mark the following step (N/A).

8.2.5 Ensure MSIV 29AOV-86A is in the as-found position recorded in Step 8.2.1.

Rev. No. 23 Page 11 of 24

MSIV FAST CLOSURE TEST (IST) ST-1B L' 8.3 MSIV 29AOV-80B Test Init 8.3.1 Record as-found position of MSIV 29AOV-80B.

(.if?TkI (position) 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 Record as-found position of MSIV 29AOV-86B.

CIcJild (position)

.Y f,

8.4.2 Ensure open MSIV 29AOV-86B.

8.4.3 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) 8.4.4 IF desired to have valve remain closed per Section F of OP-65, THEN mark the following step (N/A).

8.4.5 Ensure MSIV 29AOV-86B is in the as-found position recorded in Step 8.4.1.

Rev. No. 23 Page 12 of 24

MSIV FAST CLOSURE TEST (IST) ST-1B 8.5 MSIV 29AOV-80C Test Init 8.5.1 Record as-found position of MSIV 29AOV-80C.

(position) 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. v 8.6 EdSIV 29AOV-86C Test 8.6.1 Record as-found position of MSIV 29AOV-86C.

8.6.2 Ensure open MSIV 29AOV-86C.

8.6.3 Close and time MSIV 29AOV-86C.

Closing time s - 1 secs (IST: 3 to 5 secs)

(TS: 3 to 5 secs) 8.6.4 IF desired to have valve remain closed per Section F of OP-65, THEN mark the following step (N/A).

8.6.5 Ensure MSIV 29AOV-86C is in the as-found position recorded in Step 8.6.1.

Rev. No. 23 Page 13 of 24

MSIV FAST CLOSURE TEST (IST) ST-1B 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

'U' 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).

n 8.8.5 Ensure MSIV 29AOV-86D is in the as-found position recorded in Step 8.8.1.

Rev. No. 23 Page 14 of 24

MSIV FAST CLOSURE TEST (IST) ST-1B 9.0 RETURN TO NORMAL Init 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 di R 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

-- -.I -~~ --

MSIV F A S T CLOSURE T E S T (IST) ST-1B 9.1.3 I F all M S I V s are open, THEN the following M S I V CLOSURE T R I P relays are energized 5A-K3E at panel 09-15 5A-K3A at panel 09-15 5A-K3C at panel 09-15 5A-K3G at panel 09-15 5A-K3F at panel 09-17 5A-K3B at panel 09-17 5A-K3D at panel 09-17 5A-K3H at panel 09-17 9.1.4 Steps 9 . 1 . 1 through 9 . 1 . 3 verified by Licensed Operator.

Rev. No. 23 Page 16 of 24

MSIV FAST CLOSURE TEST (IST) ST-1B 9.2 Review and Signoff Init I , - 7 9.2.1 Test completed. 1 S;04c( 1 L

.C Date/T!irde

-1w n

4 9.2.2 Test personnel have recorded hours worked on Attachment 1.

9.2.3 Man-Hours totalled and recorded on Attachment 1.

Rev. NO. 23 Page 17 of 24

MSIV FAST CLOSURE TEST (IST) ST-1B 10.0 ACCEPTANCE CRITERIA 10.1 Level 1 Acceptance Criteria 0 Each tested valve was cycled and closed within the following stroke time limits:

IST Stroke Time Tech Spec Valve (secs) Stroke Time step (secs) 1 29AOV-80A 1 I

3 to 5 3 to 5 1 8.1.3 29AOV-8OB 3 to 5 3 to 5 8.3.3 2 9 ~ 0a~ 6- ~ 3 to 5 3 to 5 8.4.3 29AOV - 80C 3 to 5 3 to 5 8.5.3 r

~- ~ -

29AOV-86C 3 to 5 I 3 to 5 I 8.6.3 I I 29AOV-80D I I

3 to 5 I 3 to 5 I 8.7.3 29AOV-8 6D 3 to 5 3 to 5 8.8.3 L-10.2 Level 2 Acceptance Criteria None L-Rev. NO. 23 Page 18 of 24

MSIV FAST CLOSURE TEST (IST) ST-1B

~ ~~

11.0 ACCEPTANCE VERIFICATION 11.1 SNO R e v i e w 11.1.1 Verify required data has been recorded and is within required tolerances.

11.1.2 Verify required initials and signatures have been entered.

11.1.3 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.

DER number D - If necessary, initiate a PID. d/A PID number NOTE : A DER is required for instruments that exceed As Found tolerances for tracking purposes.

L 11.1.4 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 11.1.5 Identify test results:

(-) Satisfactory L) Satisfactory with corrective actions L) Unsatisfactory 11.1.6 e/Time 11.1.7 Record results in SNO log. ( L-Rev. No. 23 Page 19 of 24

MSIV FAST CLOSURE T E S T ( I S T ) ST-1B 11.2 Management S R O 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 Date/ T ime Rev. NO. 23 Page 20 of 24

MSIV FAST CLOSURE TEST (IST) ST-1B 11.3 IST Coordinator Review 11.3.1 Review test results.

11.3.2 Update records as required.

IST Coordinator Date /Time Rev. No. 23 Page 21 of 24

I MSIV FAST CLOSURE TEST ( I S T ) ST-1B 11.4 Remarks Rev. No. 23 Page 22 of 24

MSIV FAST CLOSURE TEST ( I S T ) ST-1B 12 . 0 ATTACHMENTS

i. TEST SIGNOFF LOG Rev. No. 23 Page 23 of 24

MSIV FAST CLOSURE TEST (IST) ST-1B ATTACHMENT 1 Page 1 of 1 TEST SIGNOFF LOG PRINTED NAME INITIALS HOURS WORKED I

I I l

Total Man-Hours c 5 R e v . No. 23 Page 24 of 24

-4s ==- Entersy Nuclear Northeast James A. FiePatrick Nuclear Power Plant OPERATIONS TRAINING PROGRAMS SRO NEW TASK TITLE: AOP-28/43 Procedure Execution APPL. TO JPM NUMBER REV: 0 DATE: NRC K/A SYSTEM NUMBER: .3 1 .20 JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED SUBMITTED: OPERATION Pr\/lE\*'-

\ L V I L I . .

APPROVED: v 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 IGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER Page 1 of 5

JCTb PEReORMANGt h c A S U k t 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~EMEAaUKk REQUIRED TASK INFORMATION SRO t 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. AOP-28, Operation During Plant Fires, Rev. 12 B. AOP-43. Plant Shutdown From Outside The Control Room, Rev. 28 111. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A. MFI-FP02:Z69, Fire (smoke) alarm in North Cable Run Room inserted on trigger.

B. MFI-FP02:Z57, Fire (smoke) alarm in Relay room inserted on same trigger on 30 second TD c-, C. Override on Cable Run Room High Temp Amber and C 0 2 initiation Red lamps on same trigger with 10 second TD D. ANXXW. Randomly select multiple horseshoe annunciators to crywolf. Assign to the same trigger at varying time delays up to 2 minutes 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. 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.

B. Fire Alarm, Suppression System Actuation, and verbal report confirm a large fire in the relay room.

C. Unexpected alarms confirm entry into AOP-28.

L-

- CRITICAL STEP Page 3 of 5

S/RO/NLO NEW TASK TITLE: AOP-28/43 Procedure Execution VII. INITIATING CUE 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.

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

~

STEP STANDARD EVALUATION I COMMENT

1. Receive alarms Candidate acknowledges and recognizes fire indication SAT / UNSAT in north cable run room, relay room and suppression system actuation.

2. Order fire brigade response per EAP-3 F V A l TOR SAT / UNSAT When ordered, indicate that the Fire Brigade is respondina as directed

3. Reference AOP-28 Candidate obtains AOP-28. SAT / UNSAT I I

4. Enter AOP-28 Candidate assesses that symptoms warrant AOP-28 SAT / UNSAT entry at section C.

5. Determine applicable AOP-28 Candidate determines that AOP-28 exit and AOP-43 SAT / UNSAT Attachment entry is required

6. Reference AOP-43 Candidate obtains AOP-43. SAT / UNSAT

7. Enter AOP-43 Candidate assesses that symptoms warrant AOP-43 SAT / UNSAT 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.

Page 4 of 5

i STEP STANDARD EVALUATION / COMMENT

8. C.1.4 IF Control Room evacuation is Candidate determines that a control room evacuation is SAT / UNSAT required, OR a loss of shutdown required and orders operators to perform their assigned capability from the Control Room subsections.

occurs, THEN operators perform their assigned subsection, injection must occur within 30 minutes of initial SRV actuation:

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 LCO TRACKING APPL. TO JPM NUMBER 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:

/&- OPERATION REVIEW:

Y APPROVED:

CANDIDATE NAME: S.S. NUMBER:

- JPM Completion:

Location:

(

) Simulated

) Plant

( )Performed

( )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 M b S U K t 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

-v SRO NEW TASK TITLE: TECHNICAL SPECIFICATION EVALUATION AND LCO TRACKING APPL. TO JPM NUMBER

1. SAFETY CONSIDERATIONS A. Ensure proper safety equipment and safety procedures are observed.

II. REFERENCES A. Technical Specification 3.7.6, SR 3.7.6.1 and Bases B. ST-21Q, Main Turbine Bypass Valve Cycle Test, Rev. 0 C. AP-19.01. SURVEILLANCE TESTING PROGRAM 111. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS L-' 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.

V. EVALUATOR NOTES A.

B.

VI. TASK CONDITIONS A. A plant startup is in progress, making preparations to enter Mode 2.

B. ST-21Q is in progress.

C. SNO reports that BPV-3 will not open and therefore will not meet the level 1 acceptance criteria. BPV-1 and 2 responded properly D. Candidate evaluates Tech Spec impact of the failure.

L-,

' - CRITICAL STEP Page 3 of 6

S/RO/NLO NEW TASK TITLELTASK TITLE: TECHNICAL SPECIFICATION EVALUATION VII. INITIATING CUE 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 STEP STANDARD EVALUATION I COMMENT '

I Assess the report Candidate will determine that the BPV-3 is inoperable SAT / UNSAT EVALUATOR If requested, provide blank copy of ST-21Q

2. Determine Technical Specification Candidate determines that BPV-3 has failed SR-3.7.6.1 SAT / UNSAT amlicabilitv and LCO 3.7.6 is affected.

3. Declare Bypass System inoperable Candidate determines that Applicability of LCO is not SAT / UNSAT met and LCO is therefore not applicable.

Candidate also determines that plant operation is limited to ~ 2 5 %CTP (LCO-3.0.4)

4. 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 Page 4 of 6

.TASK TITI STEP STANDARD EVALUATION / COMMENT

5. Initiate LCO tracking process EVALUATOR SAT / UNSAT Candidate prompting may be required.

Candidate obtains AP-12.08 or LCO tracking binder and determines that LCO trackina is rewired

6. Complete AP-12.08, Attachment 1 and FVAl UATOR SAT / UNSAT 2

Provide candidate with blank AP-12.08 Attachment 1 I and2 Attachment 2 of this JPM contains AP-I 2.08 I

Attachment 1 and 2 kev entries for this condition EVALUATOR: Terminate the task at this point.

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

I I

I This IS NOT a Quality R e c o r d L*

I1 AP-12-08 Rey:. No. 3 LCO TRACKING AND SAFE??' FUNCTION DET&R.M,INATION P R O G M Page ATTACHMENT 2 4 1of 49

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This Is a Quality Record

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I A?-;2.08 Re;.. No. 3 LCO TXACXING AND SAFETY FUNCTION DETERMINATIOX P R O G W A Page ATTACHMENT 1 37 of 4 9

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1 L-1 AP-i?. Oe K O TRACKING AND SAFETY FUNCTION DETERMINATION P R O G M ATTACHMENT 1 Re17. No. 3 ?age 2 of 49

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I This a Q u a l i t y Record

.e A?-12.08 LCC TTACKING AN3 S A E T ? ' FUNCTION DETERYINATZON P R O G W . ATTACHMEKT 1 Rex-. No. 3 Page 3c of 4 9

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 4 0of 45,

EAL DECLARATION JPM'S FILED WITH APPROPRIATE v

SCENARIOS

twu Nuclear Northeast b James A. FitzPatrick Nuclear Power Plant 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: 2 4 . 2 1 JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: I f j Minutes SUBMITTED: OPERATION REVIEW:

APPROVED:

CANDIDATE NAME: S.S. NUMBER:

JPM Completion: ( ) Simulated ( X ) Performed iLocation:

- -( ) Plant ( X ) Simulator DATE PERFORMED: TIME TO COMPLETE: ___ Minutes PERFORMANCE EVALUATION: ( ) Satisfactory ( ) Unsatisfactory EVALUATOR:

SIGNATURE/PRINTED CANDlDATE 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 TASK TITLE: PERFORM CONTROL ROOM ACTIONS FOR ST4OC APPL. TO JPM NUMBER

1. SAFETY CONSIDERAT DNS A. Ensure proper safety equipment and safety procedures are observed.

II. REFERENCES A. ST40C, COMPUTER OUT OF SERVICE SURVEILLANCE, Rev. 16 111. TOOLS AND EQUIPMENT A. Simulator Telephone to Instructor Console (Optional)

IV. SET UP REQUIREMENTS A. Reset the Simualtor to any at power IC with the Generator synced to the grid.

B. Insert Override Pen 2, 06PRER-98 NR RX PRESS TURB STM FLOW, to fail downscale.

u-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 mt 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. 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 N R RX PRESS TURB STM FLOW, has failed.

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STEP STANDARD EVALUATION / COMMENT

1. Candidate obtains procedure ST-40CI Candidate selects ST40C, COMPUTER OUT OF SAT / UNSAT COMPUTER OUT OF SERVICE SERVICE SURVEILLANCE.

SURVEILLANCE Candidate identifies Section 8.4, TREND RECORDER CHECK EVALllATnR Upon Section selection, hand candidate a partially performed copy of ST40C, COMPUTER OUT OF SERVICE SURVEILLANCE

2. Candidate reviews procedure NIA SAT / UNSAT

3. 8.4 Trend Recorder Check Performs step 8.4.2- verifying each of the SAT / UNSAT 8.4.2 Verify trend recorders listed following instruments:

below are trending data and the parameter recorded is indicating the expected value.

4. '7RR-53 STACK MON RANGE RAD CANDlDATE Initials for 17RR-53 STACK HIGH RANGE RAD MON SAT / UNSAT EVALUATOR monitor candidate to ensure he/she verifies indicated value is:

Page 4 of 8

SIROlNLO NEW ASK TITLE: PERFORM CONTROL ROOM ACTIONS FOR ST-QOC I I I EVALUATOR monitor candidate to ensure he/she verifies indicated value is:

6' 1 17RR-463 RADW HI RANGE VENT MON CANDlDATE Initials for 17RR-463 RADW HI RANGE VENT MON FXALUATOR monitor candidate to ensure he/she SAT I UNSAT verifies indicated value is:

17RR-455 RX BLDG VENT MON C , & U U E Initials for 17RR-455 RX BLDG VENT SAT I UNSAT 7.

(BELOW REFUEL FLOOR) MON (BELOW REFUEL FLOOR)

EVAL.LIATOR monitor candidate to ensure he/she verifies indicated value is:

0. 16-ITR-131A TORUS TEMP A CANDlOATE Initials for 16-ITR-131A TORUS TEMP A SAT I UNSAT FVAl jJAIf)Rmonitor candidate to ensure heIshe verifies indicated value is:

27PR-I 15A1 PC PRESS CLLNDlDLIiTE initials for 27PR-I 15A1 PC PRESS SAT / UNSAT 9.

FVAl LIAIQR monitor candidate to ensure heishe verifies indicated value is:

27PR-115A2 PC PRESS Initials for 27PR-115A2 PC PRESS SAT / UNSAT IO.

- F monitor candidate to ensure heIshe verifies indicated value is:

23LR-203A PC LVL CANDlDATE Initials for 23LR-203A PC LVL SAT I UNSAT 11.

EVALUATOR monitor candidate to ensure heIshe verifies indicated value is:

Page 5 of 8

(

SIROINLO NEW 4SK TITLE: PERFORM CONTROL ROOM ACTIC 3 FOR ST40C STEP STANDARD EVALUATION I COMMENT

12. 23LR-202A TORUS LVL CANDlDATE Initials for 23LR-202A TORUS LVL SAT I UNSAT EVALUATOR monitor candidate to ensure he/she verifies indicated value is:

13. 06PR-61A RX VESSEL PRESS CANDlDATE Initials for 06PR-61A RX VESSEL PRESS SAT / UNSAT E V A b l monitor candidate to ensure he/she

~ ~~~

verifies indicated value is:

14. 27PR-115B2 PC PRESS -ATE, Initials for 27PR-115B2 PC PRESS SAT / UNSAT E U L monitor candidate to ensure he/she verifies indicated value is:

15. 27PR-115Bl PC PRESS CANDlDATE Initials for 27PR-I 1581 PC PRESS SAT / UNSAT EVALUATOR monitor candidate to ensure he/she verifies indicated value is:

16. 23LR-203B PC LVL CANDlDATE Initials for 23LR-203B PC LVL SAT I UNSAT F3LALLIAIC)R monitor candidate to ensure he/she verifies indicated value is:

17. 23LR-2026 TORUS LVL C A N D l D R Initials for 23LR-2028 TORUS LVL SAT / UNSAT f3AUKEBmonitor candidate to ensure heishe verifies indicated value is:

18. 06PR-61B RX VESSEL PRESS CANDlDATE Initials for 06PR-61B RX VESSEL PRESS SAT / UNSAT FVAI_IIATC)R monitor candidate to ensure he/she verifies indicated value is:

Page 6 of 8

r S/RO/NLO NEW ASK TITLE: PERFORM CONTROL ROOM ACTIONS FOR ST-40C STEP STANDARD EVALUATION I COMMENT

19. 16-1TR-108 DW TEMP A CANDlDATE Initials for 16-1TR-108 DW TEMP A SAT I UNSAT EVALUL\TOR monitor candidate to ensure helshe verifies indicated value is:

20. IOFR-143 RHR FLOW CANnlDATE Initials for 1OFR-I43 RHR FLOW SAT / UNSAT FVAl IJATOB monitor candidate to ensure he/she verifies indicated value is:

21. 02-3LR-98 RX WTR LVL FUEL ZONE CANRKlATE Initials for 02-3LR-98 RX WTR LVL FUEL SAT l UNSAT ZONE FVAl IlATOR monitor candidate to ensure he/she verifies indicated value is:

22. 16-ITR-131B TORUS TEMP B CANDlDATE Initials for 16-ITR-131B TORUS TEMP 6 SAT l UNSAT EVI1I_UATOR monitor candidate to ensure helshe verifies indicated value is:

23. 16-1TR-107 DW TEMP B l X W R A I E Initials for 16-1TR-107 DW TEMP B SAT / UNSAT F3UMIQ.R monitor candidate to ensure he/she verifies indicated value is:

24. 16-1DPR-200 DW PRESS,TORUS CANDlDATE Initials for 16-1DPR-200 DW SAT I UNSAT PRESS, DW TO TORUS DIFF PRESS PRESS,TORUS PRESS, DW TO TORUS DlFF PRESS EVALUATOR monitor candidate to ensure helshe verifies indicated value is:

Page 7 of 8

SIROINLO NEW ASK TITLE: PERFORM CONTROL ROOM ACTIONS FOR ST-40C I I I STEP STANDARD EVALUATION/ COMMENT i

25. 02TR-165 RWR LOOP INLET TEMP CANOlDATE, Initials for 02TR-165 RWR LOOP INLET SAT / UNSAT TEMP 1

FVAl UATOR monitor candidate to ensure he/she verifies indicated value is:

Note- The dlowing Instruments are located on Panel-09-5 ~-

I

26. D6LRIPR-97 WR RX PRESS RX LVL CMURAIE Initials for 06LRIPR-97 WR RX PRESS SAT IUNSAT RX LVL F V A l I I A T Q R monitor candidate to ensure he/she verifies indicated value is:

02-3LR-85B RX WTR LVL CANDIC]ATE Initials for 02-3LR-85B RX WTR LVL SAT / UNSAT 27.

F V A l UATOR monitor candidate to ensure he/she verifies indicated value is:

2a. 06PRIFR-98 NR RX PRESS TURB CANDlOATE Determines that 06PRIFR-98 NR RX CRITICAL TASK STM FLOW PRESS TURB STM FLOW has failed downscale and reports to Supervision. SAT / UNSAT EVAL.IIATORmonitor candidate to ensure he/she verifies indicated value is:

Role Play Acting as Supervisor-Acknowledge report and direct candidate to terminate task E Y A L U X B : Terminate the task at this Doint.

Page 8 of 8

ENTERGY NUCLEAR OPERATIONS, I N C .

JAMES A. FITZPATRICK NUCLEAR POWER PLANT SURVEILLANCE TEST PROCEDURE COMPUTER om OF SHWZCE 8vRvEIwwLwcE ST-4OC RMISIOW 16 APPROVED BY:

SPONS$BLE P~OCEDUREOW&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 S u b s e c t i o n 5 . 2 ,

added S u b s e c t i o n 8 . 3 , added S t e p 8 . 9 . 4 , added S t e p 1 0 . 1 . 4 and r e v i s e d S u b s e c t i o n 1 . 2 t o p r o v i d e method f o r c a l c u l a t i n g average d r y w e l l t e m p e r a t u r e on a l o s s of p l a n t computer.

CA-02-2922-1 15 Deleted t h e requirement t o r e c o r d C a l i b r a t i o n Due Dates i n S e c t i o n s 4 and 5 p e r ODSO-31.

Revised S t e p 6 . 2 . 5 t o be c o n s i s t e n t w i t h S u r v e i l l a n c e T e s t format.

The e l e c t r i c l i f t f e a t u r e o f SRV's is no l o n g e r bypassed i n ST-40C. The f o l l o w i n g changes have been made t o s u p p o r t t h i s (ACT-01 -60461) (PCR #1 d a t e d 8/25/01) :

Deleted OP-68 from r e f e r e n c e s Added b u l l e t t o S t e p 8 . 1 . 1 as s h i f t d i s c u s s i o n i t e m .

Revised and r e t i t l e d S u b s e c t i o n 8 . 7 , a v o i d i n g r e s t r i c t i v e and unnecessary LCO.

L Revised S t e p 8 . 8 . 3 t o monitor v i c e restore.

Deleted S t e p 9 . 1 . 2 Added S t e p 8 . 2 . 1 t o e n s u r e compliance w i t h t h e SPDES p e r m i t .

C l a r i f i e d S t e p 9 . 2 . 1 c a l c u l a t i o n s are performed on Attachment 2.

Added "Average" b e f o r e " s c r e e n w e l l " i n S t e p 1 0 . 1 . 1 t o reflect t h e name as i n d i c a t e d i n S t e p 8 . 2 . 4 and Attachment 2 .

Added "Average" before " p l a n t " i n S t e p 1 0 . 1 . 2 t o reflect t h e name as i n d i c a t e d i n S t e p 8 . 2 . 5 and Attachment 2 .

Corrected t i t l e o f l a s t t a b l e column on Attachment 4 t o be consistent with action taken.

Revised S e c t i o n 1 . 2 t o i n c l u d e Improved T e c h n i c a l Specification references.

'L.'

Rev. No. 16 Page 2 of 40

A COMPUTER OUT OF SERVICE SURVEILLANCE ST-40C

.- TABLE OF CONTENTS SECT1ON PAGE 1.0 REQUIREMENTS . . . . . . . . . . . . . . . . . . 4 2.0 PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . 4

3.0 REFERENCES

. . . . . . . . . . . . . . . . . . . . . . 5 4.0 PREREQUISITES . . . . . . . . . . . . . . . . . . . . . 6 5.0 TEST EQUIPMENT, SPECIAL TOOLS AND MATERIALS . . . . . . 7 6.0 PRECAUTIONS AND LIMITATIONS . . . . . . . . . . . . . . 8 7.0 GENERAL TEST METHODS . . . . . . . . . . . . . . . . . 10 8.0 PROCEDURE . . . . . . . . . . . . . . . . . . . . . . . 11 8.1 Required Notifications and Briefings . . . . . . . . . 11 8.2 Circulating Water Temperature Check . . . . . . . . . . 12 8.3 Drywell Temperature Check . . . . . . . . . . . . . . . 14 8.4 Trend Recorder Check . . . . . . . . . . . . . . . . . 16 8.5 Balance o f Plant Check . . . . . . . . . . . . . . . . 19 8.6 Rod Worth Minimizer Inoperable Check . . . . . . . . . 19

~.--/ 8.7 Core Thermal Power Evaluation . . . . . . . . . . . . . 19 8.8 Additional Monitoring o f SRV Electric Lift Feature . . 20 8.9 Restoration . . . . . . . . . . . . . . . . . . . . . . 21 9.0 RETURN TO NORMAL . . . . . . . . . . . . . . . . . . . 22 10.0 ACCEPTANCE CRITERIA . . . . . . . . . . . . . . . . . . 23 11.0 ACCEPTANCE VERIFICATION . . . . . . . . . . . . . . . . 24 12.0 ATTACHMENTS . . . . . . . . . . . . . . . . . . . . . . 27 1 . TEST SIGNOFF LOG . . . . . . . . . . . . . . . . . 28

2. INTAKE. DISCHARGE . AND INTAKE-DISCHARGE DIFFERENTIAL TEMPERATURE CALCULATION . . . . . . . 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 L

Rev . No . 16 Page 3 of 40

SR OUT OF SERVICE SURVEILLANCE ST74OC 1 .o EQUIREMENTS 1.1 requency 3ch shift when the Emergency Plant Information Computer EPIC) is inoperable 1.2 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 1.3 ther

.3.1 Permit Requirements CP-04.03,State Pollutant Discharge Elimination System Permit 1.4 ommitments c one 2 .o 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 E l i m i n a t i o n System P e r m i t .

3.1.2 OP-64, Rod Worth Minimizer 3.1.3 ST-5E, Core Performance D a i l y S u r v e i l l a n c e 3.1.4 ODSO-17, A u x i l i a r y O p e r a t o r P l a n t Tour and O p e r a t i n g Logs 3.1.5 EP-1, EOP E n t r y and Use 3.1.6 AOP-61, S c r e e n w e l l I n t a k e Temperature High 3.2 Developmental References 3.2.1 M o d i f i c a t i o n F1-88-050, GEPAC Removal, I P - 1 ,

Ap e n d i x I Curve No. 5 Resistance VS Temperature E

Ta l e 100 P l a t i n u m RTD 3.2.2 JAF-SE-96-048, R e v i s i o n 1 , R e v i s i o n t o FSAR t o Raise Maximum Allowable Lake Temperature From 82°F t o 8 5 ° F 3.2.3 M1-97-070, SRV Electric L i f t F e a t u r e / ATWS Level 2 S e t p o i n t Change 3.2.4 FE- 36AA 3.2.5 FE- 3 6 A B 3.2.6 FE-36AC 3.2.7 FE- 36AD 3.2.8 FE-81C 3.2.9 FE-81G 3.2.10 FE-9OF 3.2.11 FE-SOH 3.2.12 FM-49A 3.2.13 SE - 9ABE 3.2.14 SE - 9ABV 3.2.15 SE-9ACG 3.2.16 SE- 9ADC Rev. No. 16 Page 5 of 40

COMPUTER OUT OF SERVICE SURVEILLANCE ST-40C NOTE: Sections 4 and 5 may be performed i n any Init order o r concurrently.

4.0 PREREQUISITES 4.1 SM has granted permission t o perform t h i s t e s t . s!

4.2 Revision Number of t h i s Workin Copy is t h e same as t h e r e v i s i o n number l i s t e d i n t h e Easter Copy o f t h e Index o f Operations Surveillance T e s t Procedures.

4.3 T e s t personnel have read t h i s procedure and are thoroughly familiar with its contents.

/-

4.4 S t a r t o f test recorded. /c hl'1hkJ ccjc Bate/Time n

4.5 S t a r t o f t e s t recorded i n SNO Log. cl/

4.6 I & C Department n o t i f i e d t h a t I&C a s s i s t a n c e is required. -!?

4.7 Required M&TE v e r i f i e d t o be within c a l i b r a t i o n and its i d e n t i f i c a t i o n number recorded i n Subsection 5 . 1 .

L Rev. No. 16 Page 6o f 40

COMPUTER OUT OF SERVICE SURVEILLANCE ST-40C 5 .O TEST EQUIPMENT, SPECIAL TOOLS AND MATERIALS 5.1 Test Equipment 5.1.1 RTD Readout and Simulator Model No. /5 I&C No. dG c h 2 5.1.2 Digital Multimeter 17R 14 i I&C No.

5.2 Special Tools Key #Orange-520 for Foxboro 09-24 & 09-25 panels I 5.3 Materials Tags for marking disconnected leads Rev. No. 16 Page 7of 40

COMPUTER OUT OF SERVICE SURVEILLANCE ST-40C L- 6.0 PRECAUTIONS AND LIMITATIONS 6.1 Precautions 6.1.1 Disconnected electrical l e a d s s h a l l be i n s u l a t e d u s i n g small s e c t i o n s o f electrical i n s u l a t i o n s l e e v i n g taped t o t h e wire i n s u l a t i o n .

Non-shrunk h e a t s h r i n k t u b i n g may also be used.

Disconnected l e a d s should n o t be i n s u l a t e d w i t h electrical t a p e , as t h e adhesive can remain on t h e conductor when removed.

NOTE : An a c c e p t a b l e method f o r i n s u l a t i n g a d j a c e n t t e r m i n a l s is electrical t a p e placed over t h e t o p of t h e t e r m i n a l board.

6.1.2 Before connecting o r d i s c o n n e c t i n g e l e c t r i c a l jumpers o r l e a d s , personnel s h a l l e n s u r e a d j a c e n t t e r m i n a l s , exposed metal, t o o l s , and t e s t equipment are i n s u l a t e d as necessary t o p r e v e n t a c c i d e n t a l s h o r t i n g o r grounding.

6.2 Limitations 6.2.1 T e s t personnel s h a l l immediately n o t i f y t h e CRS o f any f a i l u r e t o meet acceptance c r i t e r i a .

6.2.2 T e s t personnel s h a l l p r i n t name, s i g n i n i t i a l s , and e n t e r d a t e on Attachment 1 b e f o r e performing Section 8 o f t h i s t e s t .

6.2.3 When t e s t personnel complete t h e i r a s s i g n e d p o r t i o n o f t h i s t e s t , t h e y s h a l l e n t e r dose r e c e i v e d 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 t e s t has been s t a r t e d , any a d d i t i o n a l t e s t personnel s h a l l read t h i s procedure and become thoroughly familiar w i t h i t s c o n t e n t s b e f o r e performing any p o r t i o n o f t h i s t e s t .

6.2.5 M u l t i p l e workin c o p i e s o f t h i s t e s t may be used

!?

provided t h e f o lowing requirements are s a t i s f i e d :

NOTE: The work s i t e is d e f i n e d as t h e l o c a t i o n where work is c o n t r o l l e d . The l o c a t i o n o f t h e work s i t e is a t t h e d i s c r e t i o n o f t h e SNO .

A. A working copy o f t h i s t e s t s h a l l be r e t a i n e d a t t h e work s i t e .

B. The work s i t e working c o y s h a l l be t h e l e g a l K

r e c o r d f o r documenting t is t e s t .

C. Data from a l l s t e p s performed away from t h e work s i t e , i n c l u d i n g s i g n a t u r e s , i n i t i a l s ,

and recorded v a l u e s , is t r a n s c r i b e d i n t o t h e work s i t e working copy f o l l o w i n g completion o f t h e test.

Rev. No. 16 Page 9 -- of 40

COMPUTER OUT OF SERVICE SURVEILLANCE ST-40C 7.0 GENERAL TEST METHODS 7.1 T h i s t e s t c o n s i s t s o f s i x s u b s e c t i o n s which provide i n c r e a s e d monitoring o f parameters normally monitored by EPIC.

7.2 S u b s e c t i o n s 8 . 2 through 8 . 8 may be performed i n any o r d e r necessary t o f a c i l i t a t e p l a n t o e r a t i o n s . Subsection 8 . 2 i s E

performed once each hour w h i l e PIC is o u t of s e r v i c e .

Rev. No. 16 Page 10 o f 40

-. -I- ..--I

- -. I ST-40C 8.0 PROCEDURE t e p s 8 . 1 . 1 through 8 . 1 . 3 may be performed n any order or concurrently.

as on p l a n t operations. A s a- minimum,-

t h e following :

Monitoring a l t e r n a t e i n d i c a t i o n s l i s t e d i n EP-1 on a frequent and continuous basis.

Expedient i n v e s t i g a t i o n and r e p o r t i n g of a l l annunciators and alarms on panels, including panels located o u t s i d e of t h e Control Room.

Obtaining c i r c u l a t i n g water temperatures on an hourly b a s i s t o comply with t h e SPDES permit.

Core thermal d a t a , including thermal l i m i t d a t a t h a t mav n o t be a v a i l a b l e .

Making d e t a i l e d building rounds on an increased frequency.

Reporting off -normal observations upon detection.

Monitoring SRV electric l i f t a l t e r n a t e i n d i c a t i o n on a frequent b a s i s .

8.1.2 Ensure a l l on s h i f t licensed reactor operators and senior r e a c t o r operators review EP-1.

8.1.3 Notify a computer s p e c i a l i s t .

Rev. No. 16 Page 11 of 40

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COMPUTER OUT OF SERVICE SURVEILLANCE ST-40C 8.2 C i r c u l a t i n g Water Temperature Check Init NOTE 1 : Attachment 2 may be photocopied a s necessary f o r h o u r l y c i r c u l a t i n g water temperature checks.

NOTE 2: Leads t h a t were disconnected t o determine c i r c u l a t i n g water t e m p e r a t u r e s do n o t r e q u i r e re-connection u n t i l t h e computer is r e s t o r e d and t h e f i n a l set o f h o u r l y temperature checks is performed.

8.2.1 WHILE EPIC is i n o p e r a b l e , perform Subsection 8 . 2 hourly t o comply w i t h SPDES permit. NR 8.2.2 I F l e a d s have n o t been d i s c o n n e c t e d ,

TEEN d i s c o n n e c t l e a d s l i s t e d on Attachment 5 a s follows. Document performance on Attachment 5:

A. Ensure l e a d is l a b e l e d .

B. Hang t a g on l e a d s t a t i n g l e a d is disconnected p e r ST-40C.

C. Disconnect l e a d .

8.2.3 Direct I&C t o determine and r e c o r d t e m p e r a t u r e s for t h e EPIC computer p o i n t s on Attachment 2 once each hour u s i n g a n RTD Readout & Simulator o r Multimeter.

NOTE 1 : 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 NOTE 2: AOP-61 c o n t a i n s c u r r e n t e n t r y c o n d i t i o n s based on s c r e e n w e l l i n t a k e t e m p e r a t u r e .

8.2.4 Determine average s c r e e n w e l l i n t a k e temperature by completing c a l c u l a t i o n on Attachment 2 .

8.2.5 Determine average c i r c u l a t i n water i n l e t temperature by completing ca c u l a t i o n on Attachment 2 .

f L

Rev. No. 16 Page 12 of 40

COMPUTER OUT OF SERVICE SURVEILLANCE ST-40C 1

Init 8.2.6 K

Determine average plant dischar e water temperature by completing calcu ation on Attachment 2.

8.2.7 Determine intake-discharge differential temperature by completing calculation on Attachment 2.

Rev. No. 16 Page 13 of 40

COMPUTER OUT OF SERVICE SURVEILLANCE STy4OC 8.3 Drywell Temperature Check Init NOTE 1 : Attachment 3 may be photocopied a s necessary f o r d a i l y drywell temperature checks.

NOTE 2 : Leads t h a t were disconnected t o determine drywell t e m p e r a t u r e s do n o t r e q u i r e re-connection u n t i l t h e computer is r e s t o r e d and t h e f i n a l set o f d a i l y temperature checks is performed.

8.3.1 WHILE EPIC is i n o p e r a b l e , perform Subsection 8 . 3 e v e r y 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months t o comply SR 3.6.1.5.1. NR 8.3.2 IF l e a d s have n o t been d i s c o n n e c t e d ,

TEEN d i s c o n n e c t l e a d s l i s t e d on Attachment 6 as f o l l o w s . Document performance on Attachment 6 :

A. Ensure l e a d is l a b e l e d .

B. Hang t a g on l e a d s t a t i n g l e a d is disconnected p e r ST-40C.

C. Disconnect l e a d .

8.3.3 Direct I & C t o perform t h e f o l l o w i n g once every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months u s i n g an RTD Readout &

Simulator o r Multimeter and Attachment 3 .

A. I F a l e g i t i m a t e r e a d i n g can be obtained from one RTD i n a n a s s o c i a t e d DRYWELL AREA, THEN lace a checkmark on Attachment 3 R

f o r t e RTD monitored and record t h e i n d i c a t e d temperature i n t h e READING column.

B. I F n e i t h e r RTD for a n a s s o c i a t e d DRYWELL AREA is p r o v i d i n g a legitimate r e a d i n ,

R Attac ment 3 :

F TEEN erform t h e ollowing on 1 . Record "none" f o r READING 2 . L i n e o u t t h e a s s o c i a t e d WEIGHTING FACTOR 3 . Record "0" under CORRECTED VALUE Rev. No. 16 Page 14 of 40

COMPUTER OUT OF SERVICE SURVEILLANCE ST-40C 8.3.4 Determine a v e r a e drywell temperature by F

performing t h e ollowing u s i n g Attachment 3 :

A. Multiply t h e recorded READING by t h e WEIGHTING FACTOR and r e c o r d t h e r e s u l t under CORRECTED VALUE.

B. I F t h e READING f o r any DRYWELL AREA was recorded as "none" on Attachment 3 ,

THEN perform t h e f o l l o w i n g :

1 . Record t h e sum o f a l l t h e u s e d WEIGHTING FACTORS i n t h e SUM OF USED WEIGHTING FACTORS b l o c k .

2 . Record t h e sum o f a l l t h e CORRECTED VALUES i n t h e SUM OF CORRECTED VALUES block.

C. IF no DRYWELL AREAS had a READING recorded as "none" ,

THEN perform t h e f o l l o w i n g :

1 . Record " 1 " i n t h e SUM OF USED WEIGHTING FACTORS b l o c k .

2 . Record t h e sum of a l l t h e CORRECTED VALUES i n t h e SUM OF CORRECTED VALUES block.

D. Determine average drywell temperature by d i v i d i n g t h e SUM OF CORRECTED VALUES by t h e SUM OF USED WEIGHTING FACTORS and r e c o r d t h e r e s u l t as t h e AVERAGE DRYWELL TEMPERATURE on Attachment 3 .

Rev. No. 16 Page 15 of 40

COMPUTE OUT OF SERVICE SURVEILLANCE ST-40C

- 8.4 Tr nd Recorder Check Init 8 . .1 I F r e c o r d e r is n o t r e q u i r e d t o be operational for current p l a n t conditions AND t r e n d r e c o r d e r is n o t o p e r a t i n g ,

TEEN mark r e c o r d e r "NA" . NR

8. .2 V e r i f y t r e n d r e c o r d e r s l i s t e d below are t r e n d i n g d a t a and t h e parameter recorded is i n d i c a t i n g t h e expected v a l u e .

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 TORUS TEMP A 27PR-115Al PC PRESS 27PR-115A2 PC PRESS 23LR-203A PC LVL 2 3LR - 202A TORUS LVL 06PR- 6 1 A RX VESSEL PRESS 27PR-115B2 PC PRESS 27PR-115B1 PC PRESS 2 3LR - 2 0 3 B PC LVL 23LR-202B TORUS LVL 0 6 P R - 61 B RX VESSEL PRESS 16-1TR-108 DW TEMP A 10FR- 143 RHR FLOW 02-3LR-98 RX WTR LVL FUEL ZONE 16-1TR-131B TORUS TEMP B 16-1TR-107 DW TEMP B (Continued on n e x t page)

Rev. No. 16 Page 16 of 40

COMPUTE! OUT OF SERVICE SURVEILLANCE ST- 40C I

Init 16-1DPR-200 DW PRESS,TORUS PRESS, DW TO TORUS DIFF PRESS (-1 02TR-165 RWR LOOP INLET TEMP 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 27PCR-101B DRYWELL HYDROGEN/OXYGEN CONCENTRATION (-1 t

/I 68TR-102 68TR-101 DW COOL AND DW TORUS TEMP DW COOL AND DW TEMP (3

(->

I! 68TR-103 DW COOL AND DW TORUS TEMP (-1 I 27R-101 TORUS LEVEL (-1 I

111 27R-102 TORUS LEVEL (-1 (Continued on n e x t page)

- Rev. No. 16 Page 17 of 40

COMPUTER OUT OF SERVICE SURVEILLANCE ST-40C Init 8.4.2 (Cont)

PANEL 67HV-1 17RR-433 TI3 VENT MON REC PANEL 66HV-3A 17RR-456 REFUEL FLOOR EXH MON REC PANEL 6 9 H V - 1 2 17RR-458 RADWASTE VENT MON REC Rev. No. 16 Page 18 of 40

alance of P l a n t Check Init TE: Only one s e t o f Auxiliary 0 e r a t o r P l a n t 3

s e r v i c e f o r LES THAN 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

K Tour Logs is re uired i f EP C is out of omplete t h e following Auxiliary Operator P l a n t Tour ogs per ODSO-17 a t least every 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months s:

Reactor Building Tour Log Turbine Building Tour Log Radwaste Building Tour Log ubsection 8 . 6 may be marked "NA" if not a p p l i c a b l e .

Worth Minimizer Inoperable Check t h e Rod Worth Minimizer is required, t h e EPIC f a i l u r e caused t h e Rod Worth Minimizer become inoperable, N comply with Section E o f OP-64.

e Thermal Power Evaluation F a l l o f t h e following conditions e x i s t :

Core t h e r m a l power d a t a is not a v a i l a b l e from Monicore, AND Reactor power is GREATER THAN OR EQUAL TO 25%,

AND I t is a n t i c i p a t e d t h a t Monicore w i l l not be a v a i l a b l e f o r next scheduled ST-5E, THEN n o t i f y Reactor Analyst Group.

L-2 Rev. No. 16 Page 19 of 40

COMPUTER OUT OF S E R V I C E SURVEILLANCE ST-40C 8.8 A d d i t i o n a l Monitoring o f SRV Electric L i f t F e a t u r e NOTE : Bypassing t h e SRV electric l i f t f e a t u r e as a r e s u l t o f t h e l o s s o f E P I C is n o t r e q u i r e d , based on r e g u l a t o r y requirements.

A heightened o p e r a t o r awareness o f t h e s t a t u s of SRV e l e c t r i c l i f t is d e s i r e d and o b t a i n e d by more f r e q u e n t monitoring o f r e l a y room panel i n d i c a t i o n s .

Monitor i n d i c a t i o n s which r o v i d e " p r e c u r s o r " information o f E

a problem o r p o t e n t i a l p r o l e m w i t h t h e SRV electric l i f t f e a t u r e , such a s , b u t n o t l i m i t e d t o :

l o c a l s u p e r v i s o r y l i g h t s (which d e t e c t i n i t i a t i o n signals) r e s s u r e i n d i c a t i o n s (showin

!oops or if a transmitter ha 8 fifa i lone ed) o f t h e four pressure bypass s w i t c h p o s i t i o n and corresponding l i g h t i n d i c a t i o n s (if any SRV electric l i f t f e a t u r e is bypassed)

Rev. No. 16 Page 20 of 40

- -- _.-- ~ ______

COMPUTER OUT OF SERVICE SURVEILLANCE ST-40C L- 8.9 Restoration Init WEEN computer h a s been r e s t o r e d , perform t h e f o l l o w i n g :

8.9.1 Obtain f i n a l s e t o f c i r c u l a t i n g water temperature r e a d i n g s .

8.9.2 Obtain f i n a l set o f drywell t e m p e r a t u r e readings.

8.9.3 Reconnect l e a d s l i s t e d on Attachment 5 by performing t h e f o l l o w i n g . Document performance on Attachment 5 :

A. Reconnect l e a d .

B. Remove t a g s t a t i n g l e a d l i f t e d p e r ST-40C.

8.9.4 Reconnect l e a d s l i s t e d on Attachment 6 by performing t h e f o l l o w i n g . Document performance on Attachment 6 :

A. Reconnect l e a d .

B. Remove t a g s t a t i n g l e a d l i f t e d p e r ST-40C.

c-8.9.5 WHEN d i r e c t e d b SM, s e c u r e from a d d i t i o n a l

!i monitoring o f S V electric l i f t f e a t u r e .

Rev. No. 16 Page 21 of 40

COMPUTER OUT OF SERVICE SURVEILLANCE ST-40C L 9.0 RETURN TO NORMAL Init 9.1 System Restoration 9.1.1 Leads l i f t e d p e r Attachment 5 have been reconnected.

9.1.2 S t e p 9 . 1 . 1 v e r i f i e d by Licensed Operator. /.

S i g n a t u r e/Date 9.2 Review and Signoff 9.2.1 The c a l c u l a t i o n s performed i n t h e f o l l o w i n g 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 (->

8.2.6 (-1 Independent V e r i f i c a t i o n /

S i g n a t u r e/Date L-'

9.2.2 T e s t completed. /

Date/Time 9.2.3 T e s t personnel have recorded dose r e c e i v e d 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 .

\VI Rev. No. 16 Page 22 of 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 t

OR EQ AL TO 85°F per Step 8.2.4.

10.1.2 Avera e plant discharge water temperature is LESS THAN 8R EQUAL TO 112°F per Step 8.2.5.

10.1.3 Intake-dischar e differential temperature is LESS THAN OR EQUAL f 0 32.4"F per Step 8.2.7.

10.1.4 Average Drywell Temperature is LESS THAN OR EQUAL TO 10.1.5 135°F per Step 8.3.4.D.

Trend recorders listed shall be operable per I

Subsection 8.4.

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 o f 40

COMPUTER OUT OF SERVICE SURVEILLANCE STT4OC

-- 1 1 . 0 ACCEPTANCE VERIFICATION 11.1 P e r f o r m e r R e v i e w 11.1.1 V e r i f y r e q u i r e d d a t a h a s been recorded and is w i t h i n r e q u i r e d t o l e r a n c e s . (-1 11.1.2 r e q u i r e d i n i t i a l s and s i g n a t u r e s een e n t e r e d . (-1 11.1.3 I F Level 1 Acceptance Criteria w a s n o t m e t ,

THEN perform t h e f o l l o w i n g :

A. Sign o f f ST as u n s a t i s f a c t o r y .

B. Immediately n o t i f y t h e CRS.

C. I n i t i a t e a CR.

CR number D. If n e c e s s a r y , i n i t i a t e a PID.

PID number NOTE : A CR is re u i r e d f o r i n s t r u m e n t s t h a t 8

exceed A s ound t o l e r a n c e s f o r t r a c k i n g purposes.

11.1.4 IF o n l y Level 2 Acceptance Criteria was n o t m e t ,

L' THEN perform t h e f o l l o w i n g :

A. Sign o f f ST a s s a t i s f a c t o r y w i t h 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 results:

(-1 Satisfactory

(-1 S a t i s f a c t o r y with c o r r e c t i v e a c t i o n s

(-1 Unsatisfactory 11.1.6 Record r e s u l t s i n n a r r a t i v e l o g . (-1 11.1.7 Sign and r e c o r d d a t e and t i m e .

Date/Time L-Rev. No. 16 Page 24 of 40

~

COMPUTER OUT OF SERVICE SURVEILLANCE ST-40C i-, 1 1 . 2 Management SRO Review 11.2.1 Verify d a t a is w i t h i n r e q u i r e d t o l e r a n c e s . (-1 11.2.2 V e r i f y d a t a a t t a c h m e n t s , such a s r e c o r d e r p r i n t o u t s and c a l i b r a t i o n s h e e t s are included as r e q u i r e d . (-1 11.2.3 Verif r e q u i r e d i n i t i a l s and s i g n a t u r e s have een e n t e r e d . (-1 11 2 . 4 Review t e s t t o determine if t e s t 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 S a t i s f a c t o r y with c o r r e c t i v e a c t i o n s

(-1 Unsatisfactory 11.2.5 IF Level 1 acceptance c r i t e r i a is n o t s a t i s f i e d ,

TEEN immediately n o t i f y Operations Manager o r a l t e r n a t e . Record name o f person n o t i f i e d .

Person N o t i f i e d 11.2.6 I n i t i a t e r e q u i r e d c o r r e c t i v e and compensatory actions.

(-) Not r e q u i r e d

(-) Required 11.2.7 Sign and r e c o r d d a t e and time.

Management SRO Date/Time Rev. No. 16 Page 25 of 40

.U-.-

" ^

I-I.

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. TEST SIGNOFF LOG

2. INTAKE, DISCHARGE, AND INTAKE-DISCHARGE DIFFERENTIAL TEMPERATURE CALCULATION

3. DRYWELL TEMPERATURE CALCULATION

4. RESISTANCE VS TEMPERATURE TABLE

5. CIRC WATER RTD LIFTED LEAD CONTROL FORM

6. 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 Page 1 of 4 36RTD- )ESC JEAD TEMP CALC JO . REF Tee 105B2 100 a PLATINUM jCREENWELL INTAKE TEMP 19DAS-14 E+

1R18 A

105A2 SCREENWELL roe2 + B CNTAKE TEMP r082 -

100 a PLATINUM 3 9DAS- 14 roe2 P 103AlB 2W INLET TEMP F128 + C EL-E 3NDSR 33C-10A F128 -

io Q PLATINUM 0 9DAS- 15 F128 P 103A2A 2W INLET TEMP F130 +

2NDSR 33C-10A F130 -

io Q PLATINUM 09DAS- 15 F130 P 103BlA CW INLET TEMP F133 +

CNDSR 33C-10B F133 -

io Q PLATINUM 09DAS- 15 F133 P 1R19

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

INTAKE. DISCHARGE. AND INTAKE-DISCHARGEDIFFERENTIAL TEMPERATURE CALCULATION 36RTD- DESC LEAD T.B TERM TEMP CALC NO. # REF TYF= CABINET ~

103B2A CW INLET TEMP F136 + 1R18 18 F CNDSR 33C-10B F136 - 1R18 19 10 0 PLATINUM 09DAS- 15 F136 P lRl8 20 106A PLANT DISCHARGE TlOO + 1R17 WATER A TEMP TlOO - i ~7i 100 D PLATINUM 09DAS- 14 TlOO P 1R17 106B PLANT DISCHARGE TlOl + 1R17 WATER B TEMP TlOl - 1R17 5 100 Q PLATINUM 09DAS- 14 TlOl P 1R17 6 106C PLANT DISCHARGE T102 -+ 1R17 7 WATER C TEMP T102 - 1R17 8 100 Q PLATINUM 09DAS- 14 T102 P

-1R17 9 106D PLANT DISCHARGE T103 + 1R17 10 WATER D TEMP T103 - 1R17 11 100 0

- PLATINUM 09DAS- 14 T103 P 1R17 12

Connection of leads only required after final set of temperature readings I .

Time completed by I&C . Performed by I&C _. - -

Signature ST- 40C COMPUTER OUT OF SERVICE SURVEILLANCE ATTACHMENT 2 Rev. No. 16 Page 30 of 40

NOTE : Average screenwell i n t a k e temperature l i m i t is L-435°F.

8.2.3 Avera e Screenwell I n t a k e Temperature

!?

Calcu a t i o n

( A + B ) = Ave Screenwell 2 I n t a k e Temp d + - "F 2 (185OF) Init 8.2.4 Avera e C i r c u l a t i n g Water I n l e t Temperature f!

Calcu a t i o n

( C + D + E + F ) = Ave Circ 4 Water I n l e t Temp

( + + + - "F 4 Init NOTE : Avera e p l a n t d i s c h a r g e water temperature l i m i t is

<112" .

- I?

8.2.5 Avera e P l a n t Discharge Water Temperature Calcuf a t i o n

( G + H + I + J ) = Ave P l a n t Disch 4 Water Temp

( + + + -

- "F 4 (51 12°F) Init ST- 40C COMPUTER OUT OF SERVICE SURVEILLANCE ATTACHMENT 2 Rev. No. 16 Page 31 o f 40

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 not applicable.

A. Circulating inlet water tempering in progress (8.2.5 - 8 . 2 . 4 ) = intake-discharge differential temp

( - > = "F (132.4"F) Init E. Circulating inlet water tempering not in progress (8.2.5 - 8.2.3) = intake-discharge differential temp

( - > = "F (i32.4"F) Init ST-40C COMPUTER OUT OF SERVICE SURVEILLANCE ATTACHMENT 2 Rev. No. 16 Page 32 of 4 0 i/

, I I I DRYWELL RTD READING FACTOR CORRECTED VALUE AREA 16-1RTD-0 (-1 101 0.1133

(-1 120 7 (3 1 1 2 0.0621

(-1 1 1 8 SUM OF USED WEIGHTING FACTORS:

SUM OF CORRECTED VALUES: -

AVERAGE DRYWELL TEMPERATURE:

L--

~135°F ST-40C COMPUTER OUT OF SERVICE SURVEILLANCE ATTACHMENT 3 Rev. N o . 16 Page 33 of 40

RESISTANCE VS TEMPERATURE TABLE 1OD Platinum RTD Alpha = 0.00385 O / Q / O C Temperature Resistance Temperature Resistance O F Ohms "F Ohms 32 10.00 75 10.93 33 10.02 76 10.95 34 10.04 77 10.97 35 10.07 78 11 .oo 36 10.09 79 11.02 37 10.11 80 11.04 38 10.13 81 11.06 39 10.15 82 11.08 40 10.17 83 11.10 41 10.20 84 11.12 42 10.22 85 11.15 43 10.24 86 11.17 44 10.26 87 11.19 45 10.28 88 11.21 46 10.30 89 11.23 47 10.33 90 11.25 48 10.35 91 11.28 49 10.37 92 11.30 50 10.39 93 11.32 51 10.41 94 11 - 3 4 52 10.43 95 11.36 53 10.46 96 11.38 54 10.48 97 11.40 V' 55 10.50 98 11.43 56 10.52 99 11.45 57 10.54 100 11.47 58 10.56 101 11.49 59 10.59 102 11.51 60 10.61 103 11.53 61 10.63 104 11.55 62 10.65 105 11.58 63 10.67 106 11.60 64 10.69 107 11.62 65 10.72 108 11.64 66 10.74 109 11.66 67 10.76 110 11.66 68 10.78 111 11.68 69 10.80 112 11.70 70 10.82 113 11.73 71 10.84 114 11.75 72 10.87 115 11 -77 73 10.89 116 11.79 74 10.91 117 11.81 Rev. No. 16 Page 34 of 40

RESISTANCE VS TEMPERATURE TABLE 109 Platinum RTD Alpha = 0.00385 Q / Q / O C Temperature Resistance "F Ohms 118 11.83 119 11.88 120 11.90 121 11.92 122 11.94 123 11.96 124 11.98 125 12.00 126 12.03 127 12.05 128 12.07 129 12.09 130 12.11 14.

Rev. No. 16 Page 35 of 40

f ' i ATTACHMENT 5 Page 1 of 2 CIRC-WATER RT_D_.LI FTED LEAD CONTROL FORM DESC LEAD NO.

T.B. TERM t

LEAD LABEL D AND TAGGED (Steps 8 . 2 2 . A and 8 . 2 . 2 . B)

LEAD RECO:\TNECTED AND TAG REMOVE:)

(Steps 8 . 9 . 3 . A and

-I--

8 . 9 . 3 . B)

CABINET I PERFORMED INDEPENDENT PERFORMED CONCURRENT PERFORMED INDEPENDENT VERIFICATION BY DUAL BY VERIFICATION VERIFICATION Signature Signature Signature Signature Signature Signature SCREENWELL TO83 + -

1R18 13 INTAKE TEMP

~~

TO83 - lR18 14 I 09DAS-14 ~ o a 3P lRl8 15 SCREENWELL TO82 + lRl8 18 INTAKE TEMP TO82 - lRl8 19 09DAS-14 CW I N L E T TEMP CNDSR 3 3 C- 1OA 0 9DAS - 15 TO82 P F128 F128 -

F128 P

+

1R18 1R18 1R18 1R18 20 4

5 6

+

2W I N L E T F130 + 1R19 1 TEMP CNDSR 3 3 C - 1OA F130 - -

1R19 2 09DAS - 15 F130 P 1R19 3 ZW I N L E T TEMP CNDSR F133 + -

1R19 10 33C- 1 0 B F133 - 1R19 11 0 9DAS - 1 5 F133 P -

1R19 12

Connection of leads only required after final set of temperature readings Rev. No. 16 Page 36 of 40

ATTACHMENT 5 P a g e 2 of 2 C I R C WATER RTD L I F T E D LEAD CONTROL FORM DESC CABINET LEAD NO.

T.B. TERM 8 . 2 . 2 .B )

I I

LEAD LABEL D AND TAGGED (Steps 8 . 2 2 . A and VERIFICATION (Step 8.2.

I

LEAD RECOTNECTED AND TAG REMOVE)

(Steps 8 . 9 . 3 . A and 8.9.3 . B )

PERFORMED BY INDEPENDENT VERIFICATION VERIFICATION CW I N L E T TEMP CNDSR 3 3 C - 1OB F136 F136

+

-1R18 1R18 18 19

+ + --I----

+ +

0 9DAS - 15 F136 P 1R18 20 PLANT TlOO + 1R17 1 DISCHARGE

+

WATER A TlOO - 1R17 2 TEMP 0 9DAS - 14 TlOO P 1R17 7

3 PLANT DISCHARGE WATER B TEMP TlOl TlOl

+

1R17 lR17 4

5

-I--

0 9DAS - 14 TlOl P 1R17 6 PLANT T102 + -

1R17 7 DISCHARGE WATER C TEMP T102 -

1R17 8 09DAS - 14 T102 P 1R17 9 PLANT T103 + 1R17 10 DISCHARGE WATER D TEMP T103 -

1R17 11 09DAS - 14 T103 P 1-R17 12

C o n n e c t i o n of leads only required a f t e r final set of temperature readings Rev. No. 16 Page 37 of 3

COMPUTER OUT OF SERVICE SURVEILLANCE ST-40C ATTACHMENT 6 Page 1 of 2 DRYWELL RTD L I F T E D LEAD CONTROL FORM

Connection of leads only required after final set of temperature readings 4 R e v . No. 16 Page 38 of 40

i ST-40C COMPUTER OUT OF SERVICE SURVEILLANCE ATTACHMENT 6 Page 2 of DRYWELL RTD LIFTED LEAD CONTROL FORM

Connection of leads only required after final s e t of temperature readings Rev. No. 16 Page 39 of 40

ST-4OC COMPUTER OUT OF SERVICE SURVEILLANCE ATTACHMENT 6 Page 3 of DRYWELL RTD LIFTED LEAD CONTROL FORM

Connection o f leads only required a f t e r f i n a l set o f temperature readings Page 40 of .40 R e v . No. 16

Nuclear Northeast James A. FibPatrick Nuclear Power Plant OPERATIONS TRAINING PROGRAMS S/RO NEW TASK TITLE: EVALUATE SURVEILLANCE TEST ACCEPTANCE CRITERIA APPL. TO JPM NUMBER REV: 0 DATE: 5/23/03 NRC WA SYSTEM NUMBER: ,/

JAF TASK NUMBER: JAF QUAL STANDARD NUMBER:

ESTIMATED COMPLETION TIME: 2 0Minutes 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 REV1EW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER L

Page 1 of 5

JOB PERFORMANCfE M t A S U K t 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 -Validation

-Procedural Change Required ~ 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. AP-03.11, OPERABlLlN AND REPORTABILITY DETERMINATIONS

6. AP-19.01, SURVEILLANCE TESTING PROGRAM C. ST-01 6 , MSlV FAST CLOSURE TEST 111. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS

'v A. Best if conducted in the Control Room or the simulator.

B. 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. Candidate will review a completed ST-01B Surveillance Test containing test failure data that was not recorded by the performer.

6.

CRITICAL STEP L

Page 3 of 5

SIROINLO TASK TITLE:

VII. INITIATING CUE You are the Senior Nuclear Operator (SNO). Another SNO has just completed ST-01B, MSlV FAST CLOSURE TEST, and forwards it to you to complete the SNO review.

EVALllATOR Hand copy of completed Surveillance Test to candidate.

STEP STANDARD EVALUATIONI COMMENT I. 1 1.1.IVerify required data has been Candidate review all data recorded in Surveillance Test. SAT I UNSAT

-ecorded and is within required iolerances. Candidate may determine that step 8.4.3 does not meet acceptance criteria.

2. 11. I .2 Verify required initials and Candidate review all initiakignature blocks for SAT I UNSAT signatures have been entered. completion

3. 11.I .3 IF Level 1 Acceptance Criteria Candidate will recognize that step 8.4.3 does not meet SAT I UNSAT OR Level 2 LLRT valve acceptance acceptance criteria and therefore check the criteria was not met, THEN perform the Unsatisfactory box following:

EyALUATOR A. Sign off ST as unsatisfactory. When indicated, Acknowledge as the CRS and report B. Immediately notify the CRS. PID and CR are being written C. Initiate a DER.

D. If necessaw, initiate a PID.

4. 11. I .4 IF only Level 2 Acceptance This step is not applicable SAT I UNSAT 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 I

5. 11.1.5 Identify test results: Candidate will recognize that step 8.4.3 does not meet SAT/UNSAT .

(J Satisfactory acceptance criteria and therefore check the Satisfactory with corrective actions Unsatisfactory box 1 Unsatisfactorv -

Page 4 of 5

STEP STANDARD EVALUATION/ COMMENT I I 1.I

.6 Sign and record date and time. Candidate will sign, date and time the surveillance test 1 6. SAT / UNSAT 11.I.7 Record results in SNO log. EVALUATOR 4 7.

When prompted by candidate, indicate that the SNO SAT 1 UNSAT i 1

loa entrv is beina made. !j EVALUATOR: Terminate the task at this point. I

? ,. .

Page 5 of 5

ENTERGY NUCLJ3A.R OPERATIONS, INC.

L, 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 FIRST ISSUE 0 FULL REVISION n LIMITED REVISION PO

CONTINUOUS USE *

TSR *

t****************C****** .........................

TECHNICAL *

~

MSIV FAST CLOSURE TEST (ISTI ST-1B REVISION

SUMMARY

SHEET REV NO. CHANGE AND REASON FOR CHANGE 23 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-1482Section 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) 22 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

'V rev barred.

21 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 .

20 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 Page 2 of 24

M S I V FAST CLOSURE TEST (IST) ST-1B TABLE O F CONTENTS SECTION -

PAGE 1.0 REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . . - 4 2.0 PURPOSE . . . . . . . . . . . . . . . . . . . . . - . . - - 6

3.0 REFERENCES

. . . . . . . . . - . . . . . . . . . - . . . . 6 4.0 PREREQUISITES . . . . . . . . . . . . . . - . . . . . . . . 7 5.0 TEST EQUIPMENT, SPECIAL TOOLS, AND MATERIALS . . . . . . . 8 6.0 PRECAUTIONS AND LIMITATIONS . . . . . . . . . . . . . . . . 8 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 10.0 ACCEPTANCE CRITERIA . . . . . . . . . . . . . . . . . . . . 18 11.0 ACCEPTANCE VERIFICATION - . . . . . . . . . . . . . . . . . 19 12.0 ATTACHMENTS . . . . . . . . . . . . . . . . . . . . . . . . 23

1. TEST SIGNOFF LOG . . . . . . . . . . . . . . . . . . . 24 Rev. No. 23 Page 3 of 24

MSIV FAST CLOSURE TEST (ISTI ST-1B 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 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 4of 24

1.2 Technical S p o c i f i c a t i ~ s l-4. 1.2.1 surwillarrrse Rsquiraeat.

SR 3.6.1.3.6 m 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 1.3 Other ASME Section XI 1989 Edition no addenda 1.4 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.

1.5 =xxmctatioPlrr None Rev. No. 23 Page 5 of 24

MSIV FAST CLOSURE TEST (IST) ST-1B 2.0 PURPOSE To test MSIVs as required by the IST Program.

3.0 REFERENCES

3.1 Performance References None 3.2 Developmental References 3.2.1 ODSO-32, Shutdown Procedure 3.2.2 OP-1, Main Steam System 3.2.3 ASME Section XI 1989 Edition no addenda 3.2.4 Inservice Testing Program For Pumps and Valves, Third Interval 3.2.5 AP-19.05, Pump and Valve Inservice Testing 3.2.6 ESK-7A, 7B 3.2.7 FM-29A 3.2.8 1.67-97 thru 98 3.2.9 1.70-98 thru 110 3.2.10 AP-01.04, Tech Spec Related Requirements, Lists and Tables 3 -2.11 NUREG-1482 Guidelines for Inservice Testing at Nuclear Power Plants, Section 3.1.1.1 3.2.12 JD-01-123, GE REM Light Dryer Wet Transfer System Rev. No. 23 Page 6 of 24

MSIV FAST CLOSURE TEST (IST) ST-1B NOTE: Sections 4 and 5 may be performed in any Init order or concurrently.

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 revision number listed in the Master Copy of the Index of Operations Surveillance Test Procedures. '2 4.3 Test personnel have read this procedure and are thoroughly familiar with its contents.

4.4 Start of test recorded. c I i O c C q is t C-L y c.1 4Dake/Time n

4.5 Start of test recorded in SNO L o g . A!

4.6 [CTSI Reactor is shutdown, Reactor Pressure c 5 psig.

[ITS]

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 TEST EQUIPMENT, SPECIAL TOOLS, AND MATERIALS 5.1 Test Equipment Stopwatch ec/I Serial Number 5.2 Special Tools None 5.3 Ma te ri a1s None 6.0 PRECAUTIONS AND LIMITATIONS 6.1 Precautions None 6.2 Limitations 6.2.1 Test personnel shall immediately notify the SNO or C R S 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 Attachment 1.

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 8of 24

MSIV FAST CLOSURE TEST (IST) ST.-1B L- 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 e N A t l if not applicable.

6.2.7 Steps in this test marked eNR1tare not required to be initialed.

Rev. No. 23 Page 9 of 24

MSIV FAST CLOSURE TEST (IST) ST-1B 7.0 GENERAL T E S T METHODS 7.1 This test consists of eight subsections which test MSIVs as required by the IST Program.

7.2 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.

7.3 Valve closing times are measured from when t h e 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 ( T S : ).

7.4 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_...-. .- - .._.

~

MSIV FAST CLOSURE TEST (IST) ST- 1B 8.0 PROCEDURE -

Init 8.1 MSIV 29AOV-80A Test 8.1.1 Record as-found position of MSIV 29AOV-80A.

C p 4 (position) 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 Record as-found position of MSIV 29AOV-86A.

cqc rJ (position)

J!

8.2.2 Ensure open MSIV 29AOV-86A. Q 8.2.3 Close and time MSIV 29AOV-86A.

Closing time .c/. J/ secs (IST: 3 to 5 secs)

(TS: 3 to 5 secs) 8.2.4 IF desired to have valve remain closed per Section F of OP-65, THEN mark the following step (N/A).

8.2.5 Ensure MSIV 29AOV-86A is in the as-found position recorded in Step 8.2.1. n/ in-Rev. No. 23 Page 11 of 24

MSIV FAST CLOSURE TEST (IST) ST-1B 8.3 MSIV 29AOV-80B T e s t Init 8.3.1 Record as-found position of MSIV 29AOV-80B.

c; (position) 2 8.3.2 Ensure open MSIV 29AOV-80B. . .$

8.3.3 Close and time MSIV 29AOV-80B.

Closing time 7 C-t 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 Record as-found position of MSIV 29AOV-86B.

r, OpcJ (position) 8.4.2 Ensure open MSIV 29AOV-86B. x 8.4.3 Close and time MSIV 29AOV-86B.

Closing time .C secs (IST: 3 to 5 secs)

(TS: 3 to 5 secs) 8.4.4 IF desired to have valve remain closed per Section F of OP-65, THEN mark the following step (N/A).

8.4.5 Ensure MSIV 29AOV-86B is in the as-found position recorded in Step 8.4.1.

Rev. No. 23 Page 12 of 24

MSIV FAST CLOSURE TEST (IST) ST-1B 8.5 MSIV 29AOV-80C T e s t -

Init 8.5.1 Record as-found position of MSIV 29AOV-80C.

COCA

( pos'it ion) 8.5.2 Ensure open MSIV 29AOV-80C.

8.5.3 Close and time MSIV 29AOV-80C.

Closing time

.? c\ 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 MSIV 29AOV-86C T e s t 8.6.1 Record as-found position of MSIV 29AOV-86C.

f-l cp+

(position) 8.6.2 Ensure open MSIV 29AOV-86C. &

8.6.3 Close and time MSIV 29AOV-86C.

Closing time 4.-I secs 8.6.4 (IST: 3 to 5 secs)

(TS: 3 to 5 secs)

IF desired to have valve remain closed per Section F of OP-65, J?

THEN mark the following step ( N / A ) .

8.6.5 Ensure MSIV 29AOV-86C is in the as-found position recorded in Step 8.6.1.

Rev. No. 23 Page 13 of 24

MSIV FAST CLOSURE TEST (IST) ST.-1B 8.7 YSIV 29AOV-80D T e s t -

Init 8.7.1 Record as-found position of MSIV 29AOV-80D.

G,pF3 (position1 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

'L MSIV 29AOV-86D.

8.8.2 Ensure open MSIV 29AOV-86D.

8.8.3 Close and time MSIV 29AOV-86D.

Closing time 47 secs 8.8.4 (IST: 3 to 5 secs)

(TS: 3 to 5 secs)

IF desired to have valve remain closed per J?

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.

Rev. No. 23 Page 14 of 24

MSIV FAST CLOSURE TEST (IST) 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- 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 Rev. NO. 23 Page 15 of 24

M S I V F A S T CLOSURE T E S T (IST) ST-1B

9.1.3 IF a l l M S I V s a r e open, THEN t h e f o l l o w i n g M S I V CLOSURE T R I P r e l a y s are energized 5A-K3E a t pane 1 09-15 5A-K3A a t panel 09-15 5A-K3C a t panel 09-15 5A-K3G at panel 09-15 5 A - K3 F a t panel 09-17 5A-K3B a t pane 1 09-17 5A-K3D a t panel 09-17 5A-K3H a t panel 09-17 9.1.4 S t e p s 9.1.1 through 9.1.3 v e r i f i e d by L i c e n s e d O p e r a t o r .

Rev. No. 23 Page 16 of 24

MSIV FAST CLOSURE TEST (IST) ST-1B

.W 9.2 Review and Signoff Init 9.2.1 Test completed. T C C L y / 49iJ Date /+ihe 9.2.2 Test personnel have recorded hours worked o n Attachment 1.

9.2.3 Man-Hours totalled and recorded o n Attachment 1.

Rev. No. 23 Page 17 of 24

MSIV FAST CLOSURE TEST ( I S T ) ST-1B 10.0 ACCEPTANCE CRITERIA 10.1 Level 1 Acceptance Criteria Each t e s t e d v a l v e was c y c l e d and c l o s e d w i t h i n t h e f o l l o w i n g s t r o k e time l i m i t s :

I S T S t r o k e Time Tech Spec Va Ive (secs) S t r o k e Time Step (secsl I

r 29AOV-80A I I

3 to 5 I 3 to 5 I 8.1.3 29AOV-8OB 3 to 5 3 to 5 8.3.3 29AOV-86B 3 to 5 3 to 5 8.4.3 29AOV-80C 3 to 5 3 to 5 8.5.3 29AOV-86C 3 to 5 3 to 5 8.6.3 I

I 29AOV-80D I I

3 to 5 3 to 5 I 8.7.3 29AOV-86D 3 to 5 3 to 5 8.8.3 I f a v a l v e s t r o k e time does n o t meet t h e I S T l i m i t , t h e v a l v e

- s h a l l be d e c l a r e d i n o p e r a b l e and a p p l i c a b l e LCO a c t i o n s s h a l l be t a k e n . A n I S T e v a l u a t i o n which determines t h a t v a l v e o p e r a t i o n i s a c c e p t a b l e may be used t o r e s t o r e t h e v a l v e t o an o p e r a b l e s t a t u s i f Tech Spec l i m i t s a r e n o t exceeded.

10.2 Level 2 Acceptance Criteria None L,

Rev. N o . 23 Page 18 of 24

MSIV FAST CLOSURE TEST (IST) ST-1B

'e 11.0 ACCEPTANCE VERIFICATION 11.1 SNO R e v i e w 11.1.1 Verify required data has been recorded and is within required tolerances.

11.1.2 Verify required initials and signatures have been entered.

11.1.3 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.

DER number D. If necessary, initiate a PID.

PID number NOTE : A DER is required for instruments that exceed As Found tolerances f o r tracking purposes.

'L-11.1.4 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.

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 SNO Date/Time 11.1.7 Record results in SNO log.

(-1 Rev. No. 23

~~

MSIV FAST CLOSURE TEST (IST) 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. (-1 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

(-1 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.

Manageme nt SRO Date/Time Rev. No. 23 Page 20 of 24

MSIV FAST CLOSURE TEST (IST) ST-1B

-- 11.3 I S T Coordinator Review 11.3.1 Review t e s t r e s u l t s .

11.3.2 Update r e c o r d s as required.

I S T Coordinator Date /Time Rev. No. 23 Page 21 of 24

MSIV FAST CLOSURE TEST (IST) ST-1B 11.4 Remarks Rev. NO. 23 Page 22 of 24

MSIV FAST CLOSURE T E S T ( I S T ) ST-1B 12 . 0 ATTACHMENTS

1. TEST SIGNOFF LOG

-..-- Rev. No. 23 Page 23 of 24

MSIV FAST CLOSURE T E S T ( I S T ) ST-1B ATTACHMENT 1 Page 1 of 1 TEST SIGNOFF LOG Rev. No. 23 Page 24 of 24

-mh

--Entwo Nuclear Northeast James A. FitzPatrick Nuclear Power Plant OPERATIONS TRAINING PROGRAMS SlRO NEW TASK TITLE: ST-5D APPL. TO JPM NUMBER REV: 0 DATE: 5/26/03 NRC WA SYSTEM NUMBER: 7 1.7 3 7l4.4 JAF TASK NUMBER: 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:

SIGNATURE/PRINTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER Page 1 of 7

i-S/RO NEW TASK TITLE: ST-5D APPL. TO JPM NUMBER Current Update: 5/26/03 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-I 33 Previous Revision Dates:

Page 2 of 7

LS/RO NEW TASK TITLE: ST-5D APPL. TO JPM NUMBER I. SAFETY CONSIDERATIONS A. Ensure proper safety equipment and safety procedures are observed.

11. REFERENCES A. ST-5D, APRM CALIBRATION, Rev. 2 B. OP-16, NEUTRON MONITORING, Rev. 24 111. TOOLS AND EQUIPMENT A. Small Screwdriver IV. SET UP REQUIREMENTS A. >25% CTP IC with 2 loops in service, EPIC available and plant conditions stable.

B. Adjust all APRMs to an acceptable value per ST-5D.

\-

C. Adjust desired APRMs to >2% above or below desired value of ST-5D.

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.

6. The candidate should, at a minimum, identify the change in equipment status light indication when equipment operation is simulated.

C. This JPM performance data based upon E and D APRMs initially 34% low at -98% CTP VI. 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 TASK TITLE: ST-5D VII. INITIATING CUE 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. .

EVALUATOR Hand partially completed ST-5D to candidate

~~ ~~

STEP

-~

STANDARD EVALUATION I COMMENT

1. Obtain and review Procedure Candidate obtains and reviews a current CODY of ST-5D I SAT / UNSAT

2. 8.1 Procedure Performance Candidate selects subsection 8.3 SAT / UNSAT 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.

3. 8.3.1 IF core power has changed Candidate demands Official 3D at 3D keyboard by SAT / UNSAT GREATER THAN 2%, OR the control selecting:

rod pattern has changed since the last core performance program was Option 4, Run Official 3D executed, THEN demand an Official 3D Tab to Execute Program.

Select 2 on the number Dad Page 4 of 7

(

S/RO/NLO ASK TITL STEP STANDARD EVALUATION I COMMENT

4. 8.3.2 Determine APRM DR from the Candidate selects Percent Core Thermal Power with a SAT / UNSAT higher of the following values: value of -95%.

Largest MFLPD x 100 Percent core thermal power 8.3.3 [ITS] Adjust APRMs per Subsection 8.5.

5. 8.5.1 Record initial APRM readings in Candidate records values from Official 3D SAT / UNSAT Table I.

6. 8.5.2 Record DR in Table 1. Candidate records value selected in 8.3.2 SAT I UNSAT

7. 8.5.3 [ITS] Identify any APRM(s) Candidate identifies D APRM as requiring adjustment. SAT / UNSAT requiring adjustment in Table I. APRM shall be adjusted to indicate within *2%

of the DR.

8. 8.5.4 IF APRM adjustment is required, EVALUATOR SAT / UNSAT THEN perform the following for each APRM requiring adjustment: The Shift Manager desires that the APRMs be NOTE: Bypassing APRM may be bypassed for adjustments.

omitted Der SM.

9. A. Bypass the APRM channel requiring N/A SAT / UNSAT calibration Der Section E of OP-16.

Obtain and review OP-16 Candidate obtains and review OP-16 noting any SAT / UNSAT 10.

~~

cautions that mav be amlicable Select proper procedure section Candidate selects section E. 16 SAT I UNSAT 11.

12. E. 16.1 Place ApRM BYP switch in (*). At 09-5 panel, candidate selects B division joystick to SAT / UNSAT n

-~ ~~

I u. I

13. E. 16.2 Verify APRM (*) is bypassed At 09-5 panel, candidate observes white bypass lamp SAT / UNSAT using one or both of the following: for APRM D.

APRM (*) BYPASS indicating light is OR on APRM (*)

EPIC alarm indicates bypassed Candidate notes EPIC alarm typer indicates selected APRM bypass is ON Page 5 of 7

SlROlNLO NEW 4SK TITLE: ST-SD - ~

STEP STANDARD EVALUATION I COMMENT

14. E.16.3 Verify the other two APRM Candidate notes the absence of the same indications SAT / UNSAT channels associated with the same for the remaining APRMs in that RPS division (B and APRM BYP switch are in service using F).

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

15. ST-5D, 8.5.4 continued: At panel 09-14, candidate selects D APRM and SAT / UNSAT B.Ensure METER FUNCTION switch is confirms Meter Function switch is in average.

set to AVERAGE. ~~

16. C. Ensure APRM MODE switch is in the At panel 09-14, candidate selects D APRM and SAT / UNSAT OPERATE position. confirms Mode switch is in operate.

- ~-

17. NOTE: Clockwise turn raises meter At panel 09-14, candidate inserts small screwdriver into SAT / UNSAT reading; counterclockwise turn lowers upper left simulated rheostat for the D APRM.

meter reading. Candidate turns clockwise to raise indication to -95%.

D. [ITS] Turn gain adjustment control EVALllATOR (R16) on LPRM card 2-31 to obtain a In the simulator, 2-31 card can be identified but the meter readina within k2% of DR. photos do not support reading R-16

18. E. Unbypass APRM per Section E of N/A SAT / UNSAT OP-I 6.

19. Candidate obtains OP-I 6 and selects Candidate obtains procedure. SAT I UNSAT section E.17 ~~ -

20. E. 17.1 Verify the following lights for At top of paneT09-14, candidate identifies lamps for the SAT / UNSAT APRM (*) are off at panel 09- 14: D APRM.

INOP UPSCL NEUT TRIP UPSCL THERM TRIP

21. E.17.2 Place APRM BYP switch for At panel 09-5, candidate selects B division APRM SAT / UNSAT APRM (*) in center position. joystick to center position.

Page 6 of 7

S/RO/NLO NEW STEP STANDARD EVALUATION I COMMENT E.17.3 Verifi APRM (*) is returned to At 09-5 panel, candidate observes bypass lamp SAT / UNSAT 22.

service using one or both of the extinguished fo110wing: OR APRM (*) BYPASS indicating light is Candidate notes alarm typer indicates APRM bypass is Off OFF No EPIC bwassed alarm for APRM (*)

E. 17.4 Verify all three APRM channels Candidates notes above indications for the B and F SAT / UNSAT 23.

associated with the same APRM BYP APRMs.

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 APRMS 8.5.5 Record final APRM readings for Candidate record final reading. SAT / UNSAT 24.

adiusted APRMs in Table 1. I FVAl IJATOR: Terminate the task at this point.

Page 7 of 7

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT OPERATIONS SURVEILLANCE TEST PROCEDURE APRM CALIBRATION ST-5D REVISION 2 L- 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 1.0 REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . 4 2.0 PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . 5

3.0 REFERENCES

. . . . . . . . . . . . . . . . . . . . . . 5 4.0 PREREQUISITES . . . . . . . . . . . . . . . . . . . , . 6 5.0 TEST EQUIPMENT, SPECIAL TOOLS, AND UTERIALS . . . . . 6 6.0 PRECAUTIONS AND LIMITATIONS . . . . . . . . . . . . . . 7 7.0 GENERAL TEST METHODS . . . . . . . . . . . . . . . . . 9 8.0 PROCEDURE . . . . . . . . . . . . . . . . . . . . . . . 10 8.1 Procedure Performance . . . . . . . . . . . . . . . . . 10 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

APRM CALIBRATION ST-5D 1.0 REQUIREMENTS 1.1 Frequency 1CTSI Once daily while in the Run Mode CITSI NOTE : Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 ITS1 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 4of 24

APRM CALIBRATION ST-5D

'v' 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 Init order or concurrently.

4.0 PREREQUISITES 4.1 SM has granted permission to perform this test.

Revision Number of this Working Copy is the same as the 4

4.2 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. 2 4.4 Start of test recorded. TCO<L( //G Da&/Time Jhro c:\C.

d 2

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 E q u i p m e n t None 5.2 Special Tools A very small flathead screwdriver 5.3 Materials None Rev. NO. 2 Page 6of 24

APRM CALIBRATION ST-5D L- 6.0 PRECAUTIONS A N D 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. The substitute value shall be equal to the 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.

Temporary modification to provide an alternate feedwater temperature input to the plant process computer. This 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.

6.2 Limitations 6.2.1 Test personnel shall immediately notify the NCO or V

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 Attachment 1.

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 7of 24

APRM CALIBRATION ST-SD 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

'v 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 NRflare not required to be initialed.

Rev. No. 2 Page 8 of 24

.~. .. .. . .

APRM CALIBRATION ST-5D 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

APRM CALIBRATION ST-5D L

8.0 PROCEDURE Init 8.1 Procedure Performance Determine the applicable procedure subsection to perform as follows:

(-) IF reactor power is LESS THAN 25%,

THEN perform Subsection 8.2.

(-1 IF reactor power is GREATER THAN OR EQUAL TO 25%,

AND the MONICORE programs are operable, THEN perform Subsection 8.3.

(-1 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.

Rev. No. 2 Page 10 of 24

APRM CALIBRATION ST-5D UCOMl -5.1 Init 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.

c- (-1 IF result of Core Power and Flow Log program is not BETWEEN 9 and 14% power, THEN DR equals 10% power.

(-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 1 7 % 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

APRM CALIBRATION ST.-5D L-.

Init E. [CTS]

Adjust APRMs to read GREATER THAN OR

~~

EQUAL TO DR per Subsection 8.5.

[ITS]

Adjust APRMs per Subsection 8.5.

NR 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:

(-) 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 24

-_ ~. - -- .-- .

APRM CALIBRATION ST-5D L- 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

APRM CALIBRATION ST-5D L

Init 8.4 Manual Calculation by Reactor Analyst Group When Greater Than or E q u a l 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.

NR Rev. No. 2 Page 16 of 24

APRM CALIBRATION ST-5D UEXPl.6.2 Init 8.5 APRM G a i n Adjustments 8.5.1 Record initial APRM readings in Table 1.

8.5.2 Record DR 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: Bypassing APRM may be omitted per SM.

A. Bypass the APRM channel requiring calibration per Section E of OP-16. NR B. Ensure METER FUNCTION switch is set to AVERAGE. NR C. Ensure APRM MODE switch is in the OPERATE posit ion. NR 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 Rev. No. 2 Page 17 of 24

APRM C A L I B R A T I O N ST-5D Init CITSI NOTE : Tech spec acceptance c r i t e r i a f o r " F i n a l R e a d i n g "

s h a l l be w i t h i n + 2 % of DR.

8.5.5 R e c o r d f i n a l APRM readings f o r a d j u s t e d APRMs i n Table 1.

TABLE 1 APRM G A I N ADJUSTMENTS DESIRED READING R e v . No. 2 Page 18 of 24

- ~ -

_.I_-

APRM CALIBRATION ST-5D 9.0 RETURN TO NORMAL Init 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 Attachment 1.

9.2.4 Man-Hours totalled and recorded on Attachment 1.

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 Verify required data has been recorded and is within required tolerances.

11 - 1 . 2 Verify required initials and signatures have been entered.

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.

11.1.5 IF acceptance criteria is satisfied AND corrective action is required, THEN perform the following:

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 Date/Time Rev. No. 2 Page 20 of 24

APRM CALIBRATION ST-5D 11.2 Management SRO Review 11.2.1 Verify current revision of surveillance test procedure was used.

11.2.2 Verify surveillance test was completed within required test frequency.

11.2.3 Verify data tables and attachments have been properly completed.

11.2.4 Verify required data has been recorded and is within required tolerances.

11.2.5 Verify required initials and signatures have been entered.

11.2.6 Review test to determine if test results satisfy acceptance criteria.

11.2.7 Check one of the following as appropriate for test results :

(-1 Acceptance criteria satisfied.

(-1 Acceptance criteria not satisfied.

11.2.8 IF acceptance criteria is not satisfied, L 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.

11.2.9 Sign and record date and time.

Management SRO Date/T ime i

Rev. No. 2 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 23 of 24

APRM CALIBRATION ST-5D ATTACHMENT 1 Page 1 of 1 TEST SIGNOFF LOG

'V-Total Man-Hours Rev. No. 2 Page 24 of 24

mlclcl

=Entergy Nuelear Northeast James A. FitzPatrick Nuclear Power Plant 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: TIME TO COMPLETE: -Minutes PERFORMANCE EVALUATION: ( ) Satisfactory ( ) Unsatisfactory N~N~NNNNNNUUNNNNNNUNuNNNN~NNUNNUUNNU~NNNNNNmNNU-N~NNNUNNUNNNNUU~NUNNN-NNNNNNNNUN COMMENTS: (MANDATORY FOR UNSATISFACTORY PERFORMANCE)

EVALUATOR:

S IGNATURE/PRI NTED CANDIDATE REVIEW:

SIGNATURE REVIEWED BY: DOC. COMPLETE:

PROGRAM ADMINISTER

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\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 -Additional Information

-Questions and Answers -Validation

-Procedural Change Required -None Comments:

Simulator validated 5/25/03. Any IC Previous Revision Dates:

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~ - -.,c

~ U rp n t t w - u m m n l r b r iekMbcii REQUIRED TASK INFORMATION

-S/RO NEW TASK TITLE: OP-63 WEEKLY ALARM TEST APPL. TO JPM NUMBER

1. SAFETY CONSIDERATIONS A. Ensure proper safety equipment and safety procedures are observed.

II. REFERENCES A. OP-63, INTRA-PLANT COMMUNICATIONS SYSTEM, Rev. 6 111. TOOLS AND EQUIPMENT A. None IV. SET UP REQUIREMENTS A.

B.

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 mt 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. Candidate will be ordered to conduct a routine weekly test of the plant communication system.

- CRITICAL STEP c

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S/RO/NLO TASK TITLE:

VII. INITIATING CUE Perform OP-63 Weekly Alarm Testing STEP STANDARD EVALUATION I COMMENT

1. Obtain procedure Candidate obtains OP-63 and selects section E.3 SAT / UNSAT E.3.1 Candidate selects any Gai-Tronics push to talk handset SAT / UNSAT 2.

Make the following announcement over and makes the announcement.

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."

3. E.3.2 Candidate selects any Gai-Tronics push to talk handset SAT / UNSAT Announce: and makes the announcement.

"The first alarm is the Station Alarm. The first alarm is the Station Alarm."

4

SAT / UNSAT seconds.

5. E.3.4 Candidate depresses the OFF pushbutton SAT / UNSAT Silence the alarm by depressing the OFF oushbutton.

6. E.3.5 Candidate selects any Gai-Tronics push to talk handset SAT / UNSAT Announce: and makes the announcement.

"The next alarm is the Evacuation Alarm. The next alarm is the Evacuation Alarm." -_

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S/RO/NLO 4SK TITLE:

STEP STANDARD EVALUATION I COMMENT

7. E.3.6 Candidate depress EVAC pushbutton and allow audible SAT / UNSAT Depress EVAC pushbutton and allow alarm for approximately 10 seconds the alarm to sound for approximately I O seconds.

8. E.3.7 Candidate depresses the OFF pushbutton SAT / UNSAT Silence the alarm by depressing the OFF oushbutton.

E.3.8 Candidate selects any Gai-Tronics push to talk handset SAT / UNSAT 9.

Announce: and makes the announcement.

The next alarm is the Fire Alarm. The next alarm is the Fire Alarm I0. E.3.9 Candidate depress FIRE pushbutton and allow audible SAT / UNSAT Depress pushbutton and alarm for approximately I O seconds the alarm to sound for approximately 10 seconds.

11. E.3.10 Candidate depresses the OFF pushbutton SAT / UNSAT Silence the alarm by depressing the OFF oushbutton.

E.3.11 Candidate selects any Gai-Tronics push to talk handset SAT / UNSAT 12.

Announce: and makes the announcement.

This completes the test of the FVAl 1IATOR: Terminate the task at this point.

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