ML023300148

Final - Section a Operating

ML023300148
Person / Time
Site:	Salem
Issue date:	11/04/2002
From:	Diane Jackson Public Service Enterprise Group
To:	Conte R NRC/RGN-I/DRS/OSB
Conte R
References
50-272/02-301, 50-311/02-301 50-272/02-301, 50-311/02-301
Download: ML023300148 (185)

Text

NC.TQ-WB.ZZ-031 0(Z)

STATION:

SYSTEM:

TASK:

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SALEM Administrative Section Examination Perform a peer check on a completed ECP TASK NUMBER:

JPM NUMBER:

1200020301 2002 GOLF NRC RO Al ALTERNATE PATH:

APPLICABILITY:

EO =

K/A NUMBER:

IMPORTANCE FACTOR:

ROW STA

=

SRO L--

EVALUATION SETTING/METHOD:

Room with applicable references

REFERENCES:

SC.RE-RA.ZZ-0001, Rev. 0 S2.RE-RA.ZZ-0012, Rev. 58 TOOLS AND EQUIPMENT:

Calculator VALIDATED JPM COMPLETION TIME:

18 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS:

N/A APPROVAL:

BARGAINING UNIT REPRESENTATIVE

/ 'TRAINING SUPERVISOR or designee or desigrfee CAUTION:

No plant equipment shall be operated during the performance of a JPM without the following:

1. Permission from the OS or Unit CRS;

2. Direct oversight by a qualified individual (determined by the individual granting permission based on plant conditions).

3. Verification of the "as left" condition by a qualified individual.

ACTUAL JPM COMPLETION TIME:

Minutes ACTUAL TIME CRITICAL COMPLETION:

N/A Minutes JPM PERFORMED BY:

GRADE:

S.SATI-- UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE:

DATE:

2.1.25 2.8 RO 3.1 SRO Rev. 0 Nuclear Common Page I of 6

NU;. I U-W:LS.L/L-UJS1 U(L)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM:

TASK:

Administrative Perform a peer check on a completed ECP TASK NUMBER:

1200020301 INITIAL CONDITIONS:

Unit 2 is in HSB at 5471F/2235 PSIG with a reactor startup planned for this shift.

Previous Critical Conditions:

0 0

S 0

Reactor trip after 55 days at 100% power 600 ppm Boron 13000 MWD/MTU Bank D @ 217 steps Intended Critical Conditions:

0 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after the trip Bank D @ 95 steps SIMULATOR SETUP:

N/A INITIATING CUE:

Perform a peer check on a manual ECP.

Nuclear Common Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Page 2 of 10 Rev. 0

NC.TQ-WB.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM:

Administrative Perform a peer check on a completed ECP NAME:

DATE:

STEP STEP COMMENTS NO.

(*Denotes a Critical Step)

STANDARD EVAL (Required for

(#Denotes a Sequential Step)

S/U UNSAT evaluation)

Provide Candidate with a completed SC.RE-RA.ZZ-0001 START TIME:

Reviews procedure.

Reads PREREQUISITES and PRECAUTION AND LIMITATIONS Verify proper completion of Attachment 1, Estimated Critical Position Worksheet:

Review Section(s):

CUE:

Assume the data in Sections 1.0, 2.0 and 3.0 has been properly obtained and is correct.

1.0 PREVIOUS CRITICAL CONDITIONS 2.0 SHUTDOWN CONDITIONS 3.0 INTENDED CRITICAL CONDITIONS Review Section 4.0 - REACTIVITY WORTHS AT PREVIOUS CRITICAL CONDITIONS Step 4.1 Integral Rod Worth at position in 1.4.

Using Figure 4 reads < 50 pcm.

Step 4.2 Power Defect at Using Figure 2 reads approximately 1880 Power in 1.2 (100%) and Boron p

Concentration in 1.3 (600 ppm).

Page 3 of 10 TASK:

Nuclear Common Rev. 0

NC.TQ-WB.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM:

Administrative Perform a peer check on a completed ECP NAME:

DATE:

STEP STEP COMMENTS NO.

(*Denotes a Critical Step)

STANDARD EVAL (Required for

(#Denotes a Sequential Step)

S/U UNSAT evaluation)

Step 4.3 Xenon Reactivity at Time in 1.1 (48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Using Figure 6 reads approximately 2525 ago).

pcm.

CUE: If Candidate questions use of BOL curve, tell him to use the curve available.

Step 4.4 Samarium Reactivity at Time in 1.1 (48 Using Figure 1OB reads approximately 935 hours0.0108 days <br />0.26 hours <br />0.00155 weeks <br />3.557675e-4 months <br /> ago).

pcm.

Review Section 5.0 - REACTIVITY WORTHS AT INTENDED CRITICAL CONDITIONS Step 5.1 Integral Rod Worth at Position in 3.2 Using Figure 4 reads approximately 700 (D-95).

pcm.

Step 5.2 Xenon Reactivity

"* Elapsed time from 2.1 to 3.1

"* Xenon Reactivity at Time in 5.2.1 and Using Figure 8B, 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and 100%

Power in 2.2 (100%).

power reads approximately 525 pcm.

Step 5.3 Samarium Reactivity

"* Elapsed time from 2.1 to 3.1

"* Samarium Reactivity at Time in 5.3.1 Using Figure 8B, 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and 100%

and Power in 2.2 (100%)

power reads approximately 1018 pcm.

Review Section 6.0 - REACTIVITY CHANGES AND SUM Step 6.1 Integral Rod Worth (4.1)- (5.1)

-700 pcm, +/-5%

Nuclear Common TASK:

Page 4 of 10 Rev. 0

NC.TQ-WB.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE-SYSTEM:

Administrative Perform a peer check on a completed ECP STEP STEP COMMENTS NOS

(*Denotes a Critical Step)

STANDARD EVAL (Required for

(#Denotes a Sequential Step)

S/U UNSAT evaluation)

Step 6.2 Power Defect (4.2)

+1850 to +1900 pcm Step 6.3 Xenon Reactivity (5.2.2) - (4.3)

Identifies error in algebraic addition.

Correct number should be:

+ 1900 to 2100 pcm Step 6.4 Samarium Reactivity (5.3.2) - (4.4)

Identifies error in algebraic addition.

Correct number should be:

-78 to 88 pcm Step 6.5 SUM (6.1) + (6.2) + (6.3) + (6.4)

Making the corrections above, the sum is now:

(-700) + (1880) + (2000) + (-83) =

+2943 to +3251 pcm Step 7.0 Review Section 7.0 - INTENDED CRITICAL BORON CONCENTRATION DETERMINATION Step 7.1 Correction to Previous Boron due to Burnup Differences.........

Step HFP ARO Equilibrium Poison Boron Using Figure 30 reads 650 ppm 7.1.1 Concentration at Burnup in (1.5)

Step HFP ARO Equilibrium Poison Boron Using Figure 30 reads 650 ppm 7.1.2 Concentration at Burnup in (3.3)

Step Boron Concentration Difference (7.1.1)-

Calculates difference as 0 ppm 7.1.3 (7.1.2)

Step Corrected Previous Boron Concentration Calculates corrected boron as 600 ppm 7.1.4 (1.3)-(7.1.3)

TASK:

Rev. 0 Nuclear Common Page 5 of 10

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM:

Administrative TASK:

NC.TQ-WB.ZZ-0310(Z)

NAME:

DATE:

Perform a peer check on a completed ECP STEP STEP COMMENTS S

NO

(*Denotes a Critical Step)

STANDARD EVAL (Required for NO.___

(#Denotes a Sequential Step)

STANDARD_

S/U UNSAT evaluation)

Step 7.2 First Estimate of Boron Concentration Change Step Differential Boron Worth at Concentration Using Figure 12 reads (-7.85) 7.2.1 in (7.1.4) and Burnup in (3.3) for Tavg=5470F Step Boron Concentration Change Identifies error carried forward. Correct 7.2.2 (6.5)÷(7.2.1) number should be approximately (-397).

Step 7.3 Second Estimate of Boron Concentration Change Step

[2x(7.1.4) - (7.2.2)] + 2 Identifies error carried forward. Correct 7.3.1 number should be approximately 799 Step Differential Boron Worth at Concentration Identifies error carried forward. Using 7.3.2 in (7.3.1) and Burnup in (3.3) for Figure 12 reads that correct number should Tavg=547°F be approximately (-7.75).

Step Boron Concentration Change Identifies error carried forward. Correct 7.3.3 (6.5)+(7.3.2) number should be approximately (-402).

Step 7.4 Intended Critical Boron Concentration Identifies error carried forward. Correct (7.1.4)-(7.3.3) number should be approximately looz.

Step 8.0 LIMITS ON INTENDED CRITICAL CONTROL ROD POSITION Step 8.1 Rod Insertion Limit (TS 3.1.3.5)

Refers to Tech Spec which refers to Core Operating Limit Report (COLR). Verifies RIL to be Bank C at 58 steps Nuclear Common Rev. 0 Page 6 of 10

NC.TQ-WB.ZZ-031 0(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM:

Administrative TASK:

Perform a peer check on a completed ECP STEP STEP COMMENTS NO.

(*Denotes a Critical Step)

STANDARD EVAL (Required for

(#Denotes a Sequential Step)

S/U UNSAT evaluation)

Step 8.2 Intended Position + 1000 pcm (Mode 2)

Step Integral Rod Worth (5.1) + 1000 Verifies calculation to be 1700 8.2.1 Step Control Bank Position at Worth in (8.2.1)

Using Figure 4 verifies Bank C at 85 steps:

8.2.2 Bank D at 0 steps Step 8.3 Intended Position + 500 pcm (Mode 2)

Step Integral Rod Worth (5.1) + 500 Verifies calculation to be 1200 8.3.1 Step Control Bank Position at Worth in (8.3.1)

Using Figure 4 verifies Bank C at 158

8.3.2 steps

Bank D at 30 steps Step 8.4 Intended Position + 400 pcm (Mode 2)

Step Integral Rod Worth (5.1) + 400 Verifies calculation to be 1100 8.4.1 Step Control Bank Position at Worth in (8.4.1)

Using Figure 4 verifies Bank C at 173

8.4.2 steps

Bank D at 45 steps Step 8.5 Intended Position + 300 pcm (Mode 2)

Nuclear Common Page 7 of 10 Rev. 0

NC.TQ-WB.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM:

Administrative TASK:

Perform a peer check on a completed ECP STEP STEP COMMENTS NO.

(*Denotes a Critical Step)

STANDARD EVAL (Required for

(#Denotes a Sequential Step)

S/U UNSAT evaluation)

Step Integral Rod Worth (5.1) + 300 Verifies calculation to be 1000 8.5.1 Step Control Bank Position at Worth in (8.5.1)

Using Figure 4 verifies Bank C at 183

8.5.2 steps

Bank D at 55 steps Step 8.6 Intended Position - 300 pcm (Mode 2)

Step Integral Rod Worth (5.1) - 300 Verifies calculation to be 400 8.6.1 Step Control Bank Position at Worth in (8.6.1)

Using Figure 4 verifies Bank C at 225

8.6.2 steps

Bank D at 152 steps Step 8.7 Intended Position - 400 pcm (Mode 2)

Step Integral Rod Worth (5.1) - 400 Verifies calculation to be 300 8.7.1 Step Control Bank Position at Worth in (8.7.1)

Using Figure 4 verifies Bank C at 225

8.7.2 steps

Bank D at 170 steps Step 8.8 Intended Position - 500 pcm (Mode 2)

Step Integral Rod Worth (5.1) - 400 Verifies calculation to be 200 8.8.1 Step Control Bank Position at Worth in (8.8.1)

Using Figure 4 verifies Bank D at 185 steps 8.8.2 Nuclear Common Page 8 of 10 Rev. 0

NC.TQ-WB.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM:

TASK:

Administrative Perform a peer check on a completed ECP NAME:

DATE:

STEP STEP COMMENTS NO.

(*Denotes a Critical Step)

STANDARD EVAL (Required for

(#Denotes a Sequential Step)

S/U UNSAT evaluation)

Signs in the Verified By: space after Step TERMINATE JPM after signature 8.8.2 STOP TIME Terminating Cue: Candidate signs in the Verified By line and then state "This JPM is complete".

Nuclear Common Rev. 0 Page 9 of 10

NC.TQ-WB.ZZ-0310(Z)

INITIAL CONDITIONS:

Unit 2 is in HSB at 5471F/2235 PSIG with a reactor startup planned for this shift.

Previous Critical Conditions:

0 S

0 S

Reactor trip after 55 days at 100% power 600 ppm Boron 13000 MWD/MTU Bank D @ 217 steps Intended Critical Conditions:

48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after the trip Bank D @ 95 steps INITIATING CUE:

Perform a peer check on a manual ECP.

Nuclear Common Page 10 of 10

SInternal use univ Page 1 of 2 PSEG NUCLEAR L.L.C.

SALEM GENERATING STATION/REACTOR ENGI*E*IURNQ SC.RE-RA.ZZ-0001(Q) - REV. 0 ESTIMATED CRITICAL POSITION CONTRO I USE CATEGORY: I COPY REVISION

SUMMARY

Biennial Review performed: Yes X No This revision combined procedures Si.RE-RA.ZZ-O001 (Q) and S2.RE-RA.ZZ-0001(Q),

therefore, all references were revised to incorporate both Salem Stations.

The requirements related to independent verification were strengthened - Steps 5.1.5 and 5.1.6 were added. Required signatures were added to: Attachment 1, page 5; and Attachment 2.

The requirements related to Supervisor - Reactor Engineering review and approval were strengthened - Step 5.1.7 was added and a required signature was added to Attachment 1, page

5.

The titles were changed from "SNSS\\NSS" to "OS\\CRS" throughout the procedure to reflect current terminology.

Deleted "Xenon Code," "ECP Code," and "RXCALC Program" as data sources throughout the procedure. Added preferred data sources "Power Distribution Monitoring System (PDMS)" and "Advanced Nodal Code (ANC)."

Old Steps 5.1.2 - 5.1.4 were moved to the Precautions Section (3.14 - 3.16).

Precaution 3.17 was added to provide additional clarification.

Step 3.5 - the Core Operating Limits Report was added to provide the specific location of the referenced insertion limit.

IMPLEMENTATION REQUIREMENTS Effective Date 1(//

/0/

APPROVED:

NA Manager Nuclear Fuels/Reactor Engineering (or Designee)

Date t'*ry Internal Use Only page I of 2

PSEG Internal Use Only Page 2 of 2 SC.RE-RA.ZZ-OOO1(Q) - REV. 0 ESTIMATED CRITICAL POSITION Step 3. 11 --the value was changed from 50 pcm to 100 pcm to allow greater flexibility.

The note prior to Step 5.1 was added to reflect preferred use of PDMS.

The old note prior to Attachment 1, Step 5.3.2, related to adding 588 pcm to the value obtained from the figure was deleted. It is no longer applicable with the development of new figures.

The note prior to step 5.1.1.C.2 was added recommending placing Control Bank D at approximately 100 steps.

"Use HFP" was added to Steps 5.1.1.D.4 and 5.1.1.E. 1 for clarification.

Steps 5.1.1.D.3, 5.1.1.D.4, 5.1.1.E.2, and 5.1.1.E.3 were changed to a conditional step format.

Step 5.1..D.4.a - changed from "use 588 pcm" to "use Figures 10 A, B, C of SI(2).RE RA.ZZ-00 12(Q), Figures" to incorporate the new figures.

Step 5.1.1.E.2.a - reference was changed from "Figure 8" to "Figure 8 A, B, C" to incorporate the new figures.

Step 5.1.1.E.3. a - reference was changed from "Figure 10" to "Figure 10 A, B, C" to incorporate the new figures.

Step 5.1.1.H. 1 - the reference was changed from T/S "3.1.3.5 Figure 3-1-1" to "Core Operating Limits Report (COLR) Figure 1 (T/S 3.1.3.5)" to reflect current T/S wording.

Steps 5.1.2 and 5.1.3 were added to require calculation of a second ECP.

Step 5.2.2 - The information related to records retention was deleted.

Step 6.1 - the reference was changed from NAP-3 to NAP-i 1. The cross-reference was also changed.

7. 1.1.B - Cross-reference was revised to correspond to T/S wording.

Step 1.3 and item 7.1.2.D - Cross-reference was updated to SC.RE-IO.ZZ-0002(Q). Item 7.1.2.F was added.

Numerous minor editorial changes were made throughout the document to comply with the writers guide. These changes were not identified with revision bars.

PSEG Internal Use Only Page 2 of 2

SC.RE-RA.ZZ-000 I(Q)

ESTIMATED CRITICAL POSITION TABLE OF CONTENTS Section Title Page 1.0 P U R P O S E........................................................................................................

2 2.0 PR E R E Q U ISIT E S.........................................................................................

. 2 3.0 PRECAUTIONS AND LIMITATIONS........................................................

2 4.0 EQUIPMENT/MATERIAL REQ IRED......................................................

4 5.0 P R O C E D U R E.................................................................................................

4 5.1 Estim ated C ritical Position..................................................................

4 5.2 Com pletion and R eview....................................................................

10 6.0 R E C O R D S....................................................................................................

1 1 7.0 R E F E R E N C E S..............................................................................................

11 ATTACHMENTS Estimated Critical Position Work Sheet.........................................................

12 Completion Sign-Off Sheet...........................................................................

18 Salem Common Rev. 0 Page I of 18

SC.RE-RA.ZZ-OOO1(Q) 1.0 PURPOSE 1.1 To calculate plant conditions that will achieve criticality. The conditions ensure adequate shutdown margin in the event of a reactor trip. The estimated conditions also avoid unanticipated criticality in the event of instrument failure.

1.2 To satisfy the requirements of Technical Specification (T/S) Surveillance 4.l1.1.1.1.c in Mode 2.

1.3 This procedure is to be completed prior to approach to criticality during the operating cycle. This procedure is NOT applicable to the initial approach to criticality following a Refueling Outage. The Estimated Critical Position following a Refueling Outage is predicted IAW SC.RE-IO.ZZ-0002(Q), Low Power Physics Testing and Power Ascension.

2.0 PREREQUISITES e62.1 The plant is in hot standby (Tave = 5470 F).

3.0 PRECAUTIONS AND LIMITATIONS f,*3.2

-3.3 3.4

/_. _3.5

/3.6 The NAME, INITIALS, and SIGNATURES of all personnel performing steps in this procedure, and the DATE of performance shall be recorded on Attachment 2.

Conditional steps shall be evaluated by the user and if not applicable marked "N/A." Conditional steps include words IF, WHEN, and OR.

All deficiencies and corrective actions taken during the performance of this procedure, including Termination, shall be documented in the Comments section of Attachment 2.

Non-conditional steps which are evaluated as being not applicable shall be marked "N/A," initialed by the Reactor Engineer, and clearly explained in the Comments section of Attachment 2.

The critical control rod position shall be above the hot zero power minimum insertion limit of the Core Operating Limits Report (COLR) IAW T/S 3.1.3.5.

This procedure does not correct for temperatures other than 547°F.

Criticality must be anticipated any time there is an insertion of positive reactivity (e.g. RCCA withdrawal, Boron Dilution, etc.).

Salem Common Page 2 of 18 Rev. 0

SC.iRE-RA.ZZ-ooo (Q) j

1

/.~

39 3.10 3.1 3.12 The actual critical configuration shall be within +/- 1000 pcm of the estimated configuration.

Chemical analysis is used to verify boron concentrations.

IF the estimated time of criticality changes such that the amount of reactivity change introduced is greater than +/-100 pcm, TIHEN a new estimated critical position shall be calculated.

Reactivity data will change with fuel exposure, fission product build up, calculational improvements, etc.

3.13 All previous critical data should be from the same point in time. This is especially pertinent for data collected during transients. [C0498]

3.14 15 3
.16

...- g 17 The Supervisor - Reactor Engineering may substitute reactivity worths from sources not specifically mentioned in Section 5.1 at his/her discretion.

Substitutions of this type shall be noted where entered on Attachment I and shall be initialed by the Supervisor - Reactor Engineering and the OS/CRS prior to criticality.

Each reactor startup will be guided by plotting an Inverse Count Rate Ratio Plot IAW SC.RE-RA.ZZ-0002(Q), Inverse Count Rate Ratio During Control Rod Withdrawal.

REFER to S 1(2). OP-IO.ZZ-0003 (Q), Hot Standby to Minimum Load, for corrective actions if any of the following occur:

Criticality is achieved prior to the rod position in Attachment 1, Step 8.1.

Criticality is achieved prior to the rod position in Attachment 1, Step 8.3.2.

Criticality is not yet achieved when the rod position in Attachment 1, Step 8.8.2 is reached.

For transient xenon conditions, increased accuracy may be obtained by interpolating between Figures 12 and 13 of S1(2).RE-RA.ZZ-0012(Q), Figures.

Salem Common 3).8 Data chosen for the previous critical conditions should be the best available data, not necessarily the most recent. Conditions that yield the best ECP results are steady state operation and previous hot zero power conditions. [C04981 Page 3 of 18 Rev. 0

SC.RE-RA.ZZ-.O01 (Q) 4.0 EQUIPMENT/MATERIAL REQUIRED Calculator Approved Computer Code 5.0 PROCEDURE 5.1 Estin

/

- 5.1.1 nated Critical Position COMPLETE Attachment 1, Estimated Critical Position Worksheet, Steps 1.1 - 8.8.2 as follows:

A.

DETERMINE appropriate Previous Critical Conditions: [C04981 I CHOOSE the best conditions available, not necessarily the most recent.

REFER to the following for examples of previous conditions which yield the best ECP results:

Previous Hot Zero Power data Steady state operation data AVOID using data collected during or just following a transient power history, if possible.

OBTAIN all previous critical data from the same point in time. This is especially pertinent for data collected during transients.

Salem Common NOTE If available, consider using the Power Distribution Monitoring System (PDMS) IAW SC.RE SO.NIS-000 1(Q), BEACON Operation & Calculation Verification, to satisfy the requirements of this procedure.

1.

.Z- /

2

3.

/*4.

Page 4 of 18 Rev. 0

sC.R-RA.ZZ-OOOI(Q)

S5.

OBTAIN Date, Time, Power Level, Boron Concentration, and Control Bank position data from any of the following sources:

Control Room Logs Calorimetric Calculations Past ECPs Control Room Charts

+

Chemistry Logs Power Distribution Monitoring System (PDMS)

.6.

OBTAIN Cycle Exposure data B.

OBTAIN Shutdown Conditions from any of the following sources:

Control Room Logs Control Room Charts Shutdown Margin Calculations Power Distribution Monitoring System (PDMS) f"*

C.

DETERMINE Intended Critical Conditions:

• J 1. CHOOSE a Date and Time that is within four hours prior to achieving criticality lAW T/S 4. 1. 1.1.1.c.

NOTE It is recommended that Control Bank D be set at approximately 100 steps (consider the following recommendations: BOL 85-95 steps, MOL 90-130 steps, and EOL 125-145 steps).

This ensures adequate control rod height for AFD control and should be consistently greater than 500-pcm rod height.

6Y-W

2.

CHOOSE a Control Bank Position that allows for the full

+/-500 pcm of rod motion allowed by the administrative limit.

3.

OBTAIN Cycle Exposure data.

Salem Common Page 5 of 18 Rev. 0

• D.

SC.RE-RA.ZZ-000 1(Q)

DETERMINE Reactivi:y Worths at Previous Critical Conditions:

1 OBTAIN Integral Rod Worth from any of the following sources:

Figure 4 of SI(2).RE-RA.ZZ-0012(Q), Figures (use HFP)

Advanced Nodal Code (ANC)

Nuclear Design Report (NDR) 9--2.

OBTAIN Power Defect from any of the following sources:

Figure 2 of S 1(2).RE-RA.ZZ-0012(Q), Figures Advanced Nodal Code (ANC)

Nuclear Design Report (NDR)

A".';f3.

OBTAIN Xenon Reactivity from an applicable source:

a.

IF equilibrium xenon conditions existed at the previous critical conditions, THEN use Figure 6 of S 1(2).RE-RA.ZZ-00 12(Q).

,JŽ

b.

IF equilibrium xenon conditions did NOT exist at the previous critical conditions, THEN use any of the following:

Power Distribution Monitoring System (PDMS)

Advanced Nodal Code (ANC)

+

Nuclear Design Report (NDR)

4.

OBTAIN Samarium Reactivity from an applicable source:

IF equilibrium samarium conditions existed at the previous critical conditions, THEN use Figure 10 A, B, C of S1(2).RE-RA.ZZ-0012(Q), Figures.

Salem Common Page 6 of 18 Rev. 0

E.

b.

Nuclear Design Report (NDR)

DETERMINE Reactivity Worths at Intended Critical Conditions:

1.

OBTAIN Integral Rod Worth from any of the following sources:

Figure 4 of SI(2).RE-RA.ZZ-0012(Q), Figures (use HZP)

Advanced Nodal Code (ANC)

Nuclear Design Report (NDR)

2.

OBTAIN Xenon Reactivity from an applicable source:

f-p.,



a.

Z)A /

b.

IF the shutdown was due to a reactor trip and equilibrium xenon conditions existed prior to the reactor trip, THEN use Figure 8 A, B, C of S 1(2).RE-RA.ZZ-0012(Q), Figures.

IF the shutdown was NOT due to a reactor trip OR equilibrium xenon conditions did NOT exist prior to the reactor trip, THEN use any of the following:

Power Distribution Monitoring System (PDMS)

Advanced Nodal Code (ANC)

"I Nuclear Design Report (NDR)

3.

OBTAIN Samarium Reactivity from an applicable source:

a.

IF equilibrium samarium conditions existed at the time of shutdown, THEN use Figure 10 A, B, C of S l(2).RE-RA.ZZ-0012(Q), Figures.

Salem Common sC.RE-RA.ZZ-OOOI(Q)

IF equilibrium samarium conditions did NOT exist at the previous critical conditions, THEN use any of the following:

Power Distribution Monitoring System (PDMS)

Advanced Nodal Code (ANC)

Page 7 of 18 Rev. 0

) J A b.

/7 ZF.

C-7--/- oG CALCULATE Reactivity Changes and SUM as directed on, Steps 6.1 - 6.5.

DETERMINE Intended Critical Boron Concentration: [C04981 1.

OBTAIN HFP ARO Equilibrium Boron Concentrations from Figure 30 of S 1(2).RE-RA.ZZ-0012(Q), Figures.

CALCULATE the Corrected Previous Boron Concentration (due to burnup differences between the previous and intended critical conditions) as directed on, Step 7.1.

OBTAIN Differential Boron Worths from any of the following sources:

4 Figure 12 of S 1(2).RE-RA.ZZ-0012(Q), Figures Figure 13 of SI(2).RE-RA.ZZ-0012(Q), Figures Power Distribution Monitoring System (PDMS)

Advanced Nodal Code (ANC)

Nuclear Design Report (NDR)

CALCULATE the First Estimate of Boron Concentration Change as directed on Attachment 1, Step 7.2.

CALCULATE the Second Estimate of Boron Concentration Change as directed on Attachment 1, Step 7.3.

CALCULATE the Intended Critical Boron Concentration as directed on Attachment 1, Step 7.4.

Salem Common rl4t"4.

sC.R.E-RA.ZZ-O00 I(Q)

IF the shutdown was NOT due to a reactor trip OR equilibrium samarium conditions did NOT exist prior to the reactor trip, THEN use any of the following:

Power Distribution Monitoring System (PDMS)

Advanced Nodal Code (ANC)

Nuclear Design Report (NDR)

S2.

Page 8 of 18 Rev. 0

sC.RE-RA.ZZ-OOO1(Q)

/

II-,.

- 5.1.2

-." 5.1.3 AJ..-5.1.4

,*5.1.5 H.

DETERMINE Limits on Intended Critical Control Rod Position:

1.

OBTAIN the Rod Insertion Limit for 0% RTP from either of the following sources for Attachment 1, Step 8.1:

Figure 14 of SI(2).RE-RA.ZZ-0012(Q), Figures Salem 1(2) Core Operating Limits Report (COLR)

Figure 1 (T/S 3.1.3.5)

.2.

OBTAIN Control Bank Positions from either of the following sources for Attachment 1, Steps 8.2 through 8.8:

Figure 4 of S 1 (2).RE-RA.ZZ-0012(Q), Figures Nuclear Design Report (NDR)

USE a different methodology to CALCULATE a second Estimated Critical Position IAW with Step 5.1.1.

ENSURE the Estimated Critical Positions calculated in Steps 5.1.1 and 5.1.2 are within 100 pcm. RECONCILE any differences greater than 100 pcm.

COMPLETE Attachment 2, Section 1.0 and 2.0.

DIRECT a Qualified Individual to PERFORM an independent verification of Attachment 1, Steps 1.1 - 8.8.2 for each calculated Estimated Critical Position.

5.1.6 Independent Verifier COMPLETE Attachment 1 and Attachment 2, Section 3.0. FORWARD this procedure to the Supervisor - Reactor Engineering for review and approval to this point.

5.1.7 Supervisor - Reactor Engineering REVIEW this procedure to this point for completeness and accuracy. COMPLETE Attachment 1 and FORWARD the procedure to the OS/CRS for review to this point.

5.1.8 OS/CRS REVIEW this procedure to this point and COMPLETE.

5.1.9 WHEN Reactor Power is 10-8 amps, as indicated on the Intermediate Range NIS, THEN COMPLETE Attachment 1, Steps 9.1 - 9.3.3.

Salem Common Page 9 of 18 Rev. 0

5.2 Completion and Review 5.2.1 COMPLETE Attachment 2, Section 1.0 and 2.0, and FORWARD this procedure to the OS/CRS for review.

5.2.2 OS/CRS REVIEW this procedure for completeness and COMPLETE, Section 4.0.

END OF PROCEDURE SECTION Page 10 of 18 sC.RE-RA.Z7-O00 I(Q)

Salem Common Rev. 0

sC.IRE1-RA.ZZ-0001(Q) 6.0 RECORDS 6.1 Retain the following JAW NC.NA-AP.ZZ-001 1(Q), Records Management Program:

+

+

7.0 REFERENCES

7.1 Cross-

References:

7.1.1 Technical Specifications (T/S):

A.

Section 4.1.1.1.1.c, Reactivity Control Systems - Boration Control B.

Section 3.1.3.5, Reactivity Control Systems - Control Rod Insertion Limits

7.1.2 Procedures

A.

NC.NA-AP.ZZ-001 1(Q), Records Management Program B.

SC.RE-RA.ZZ-0002(Q), Inverse Count Rate Ratio During Control Rod Withdrawal C.

S 1(2).OP-IO.ZZ-0003(Q), Hot Standby to Minimum Load D.

SC.RE-IO.ZZ-0002(Q), Low Power Physics Testing and Power Ascension E.

S1(2).RE-RA.ZZ-0012(Q), Figures F.

SC.RE-SO.NIS-0001(Q), BEACON Operation & Calculation Verification

7.2 Commitments

C0498, NSO INCI 93-058 Salem Common Page 11 of 18 Rev. 0

SC.RE-RA.ZZ-OO 1(Q)

ATTACHMENT 1 ESTIMATED CRITICAL POSITION WORKSHEET Page 1 of 6 PREVIOUS CRITICAL CONDITIONS Date: //-

/-"

c?

Power Level Boron Concentration Control Bank Position Cycle Exposure SHUTDOWN CONDITIONS Time

/c491090 Bank (

Bank E 1.0 1.1 1.2 1.3 1.4 1.5 2.0 2.1 2.2 3.0 3.1 3.2 DaCte rol Posie44ti Control Bank Position 3.3 Cycle Exposure A__)V__%RTP

• 0*

ppm e

steps

/3 O

MWD/MTU Time Q20O 0 Time 4IAJ (A_

%/min

/ &V

%RTP Time c*e,. oo Bank C r,3 steps Bank D.____

steps

_______MWD/MTU Salem Common NOTE See procedure Section 5.1 for comprehensive directions for completing this attachment.

The attachment itself no longer contains the applicable Figure numbers. This information is now contained in Section 5.1 of the procedure.

Reactor Trip Date.b OR Orderly Shutdown Date 411,4 Approximate Shutdown Rate Power Level Prior to Shutdown INTENDED CRITICAL CONDITIONS S ('*.RE-RA.ZZ-000 (Q)

Page 12 of 18 Rev. 0

ATTACHMENT 1 ESTIMATED CRITICAL POSITION WORKSHEET Page 2 of 6 4.0 REACTIVITY WORTHS AT PREVIOUS CRITICAL CONDITIONS 4.1 Integral Rod Worth at Position in (1.4)

N pcm 4.2 Power Defect at Power in (1.2) and Boron Concentration in (1.3)

(+)

o pcm 4.3 Xenon Reactivity at Time in (1.1)

(-).

iP

?--

pcm NOTE If previous conditions were steady state, use Figure 10 A, B, C.

4.4 Samarium Reactivity at Time in (1.1)

(-)__

3__s" pcm 5.0 REACTIVITY WORTHS AT INTENDED CRITICAL CONDITIONS 5.1 Integral Rod Worth at Position in (3.2)

(+)

t...

pcm 5.2 Xenon Reactivity 5.2.1 Elapsed Time from (2.1) to (3.1) 70 hrs 5.2.2 Xenon Reactivity at Time in (5.2.1) and Power in (2.2)

(_)

pcm 5.3 Samarium Reactivity 5.3.1 Elapsed Time from (2.1) to (3.1)

'9' hrs 5.3.2 Samarium Reactivity at Time in (5.3.1) and Power in (2.2)

(-) 4

/f pcm Salem Common sC.RE-RA.ZZ-O001 (Q)

Rev. 0 Page 13 of 18

ATTACHMENT 1 ESTIMATED CRITICAL POSITION WORKSHEET C e

.0 Page 3 of 6 A-J"E 6.0 REACTIVITY CHANGES AND SUM 6.1 Integral Rod Worth (4.1)-(5.1) pcm 6.2 Power Defect (4.2) 4-AdV'O'*

pcm 6.3 Xenon Reactivity (5.2.2)-(4.3) pcm (4,,

jc*

6.4 Samarium Reactivity (5.3.2)-(4.4)

Y_3_ pcm

)

6.5 SUM (6.1)+(6.2)+(6.3)+(6.4)

"7/7 pcm (3

/7) 7.0 INTENDED CRITICAL BORON CONCENTRATION DETERMINATION 7.1 Correction to Previous Boron due to Burnup Differences between Previous and Intended Critical Conditions 7.1.1 HFP ARO Equilibrium Poison Boron Concentration at Bumup in (1.5) ppm 7.1.2 HFP ARO Equilibrium Poison Boron Concentration at Burnup in (3.3) ppm 7.1.3 Boron Concentration Difference (7.1.1)-(7.1.2) ppm 7.1.4 Corrected Previous Boron Concentration (1.3)-(7.1.3) 64_00 ppm 7.2 First Estimate of Boron Concentration Change 7.2.1 Differential Boron Worth at Concentration in (7.1.4) and Bumup in (3.3) for Tavg=547°F pcm/ppm 7.2.2 Boron Concentration Change (6.5)-7.2.1) 7/

ppm Salem Common sC.RE-RA.ZZ-000 I(Q)

Page 14 of 18 Rev. 0

SC.RE-RA.ZZ-O00 (Q)

ATTACHMENT I ESTIMATED CRITICAL POSITION WORKSHEET Page 4 of 6 7.3 Second Estimate of Boron Concentration Change 7.3.1

[2 X (7.1.4) - (7.2.2)] - 2 7.3.2 Differential Boron Worth at Concentration in (7.3.1) and Burnup in (3.3) for Tavg=5470 F 7.3.3 Boron Concentration Change (6.5)+(7.3.2) 7.4 Intended Critical Boron Concentration (7.1.4)-(7.3.3) ppm

(

eAZ (ALUE pcm/ppm "7-7" ppm 09 9ppm

(/, ¢0=

8.0 LIMITS ON INTENDED CRITICAL CONTROL ROD POSITION 8.1 Rod Insertion Limit (TS 3.1.3.5) 8.2 Intended Position + 1000 pcm (Mode 2) 8.2.1 Integral Rod Worth (5.1) + 1000 8.2.2 Control Bank Position at Worth in (8.2.1) 8.3 Intended Position + 500 pcm 8.3.1 Integral Rod Worth (5.1) + 500 8.3.2 Control Bank Position at Worth in (8.3.1) 8.4 Intended Position + 400 pcm 8.4.1 Integral Rod Worth (5.1) + 400 8.4.2 Control Bank Position at Worth in (8.4.1)

Bank C

,94_

steps pcm Bank C steps Bank D 0

steps pcm Bank C

/___

steps Bank D 1_(j2 steps 11/90 -pcm Bank C J73 steps Bank D IS.-

steps Page 15 of 18 Salem Common Rev. 0

ATTACHMENT 1 ESTIMATED CRITICAL POSITION WORKSHEET Page 5 of 6 8.5 Intended Position + 300 pcm 8.5.1 Integral Rod Worth (5.1) + 300 8.5.2 Control Bank Position at Worth in (8.5.1) 8.6 Intended Position - 300 pcm 8.6.1 Integral Rod Worth (5.1) - 300 8.6.2 Control Bank Position at Worth in (8.6.1) 8.7 Intended Position - 400 pcm 8.7.1 Integral Rod Worth (5.1) - 4(

8.7.2 Control Bank Position at Wo in (8.7.1) 8.8 Intended Position - 500 pcm 8.8.1 Integral Rod Worth (5.1)- 5C 8.8.2 Control Bank Position at Wo:

in (8.8.1)

Completed By: _

Verified By:

Approved By:

Reviewed By:

/i6O pcm Bank C 14P3 steps Bank D 5Ž5.

steps 4/0 pcm Bank C steps Bank D

/,

steps pcm Bank C steps BankD D

steps pcm L L41 Bank D steps Date /-

'Time 1470V Date Time Date Time Supervisor - Rx. Eng.

Date Time Salem Common OS/CRS sC.RE-RA.ZT-0001 (Q)

Page 16 of 18 Rev. 0

SC-RE-RA.ZZ-0001(Q)

ATTACHMENT 1 ESTIMATED CRITICAL POSITION WORKSHEET Page 6 of 6 9.0 9.1 9.2 CONFIGURATION AT 10-8 AMPS Date Boron Concentration 9.3 Control Bank Position 9.3.1 Actual Position 9.3.2 Minimum Position (8.1) 9.3.3 Maximum Position (8.8.2)

Completed By:

Reviewed By:

OS/CRS Time RCS ppm PZR ppm Bank C steps Bank D steps Bank C steps Bank D steps Time Date Date Time Salem Common Page 17 of 18 Rev. 0

SC.RE-RA.zZ-O001(Q)

ATTACHMENT 2 COMPLETION/SIGN-OFF SHEET Page 1 of 1

1.0 COMMENTS

(Procedure deficiencies shall be documented with corrective actions in this section.)

2.0 SIGNATURES

Name (Print)

Initials Signature Date 3.0 INDEPENDENT VERIFICATION:

Name (Print)

Initials Signature Date 4.0 FINAL REVIEW AND APPROVAL:

This procedure with Attachments 1 and 2 has been reviewed for completion. All deficiencies with their associated corrective actions are clearly recorded in the COMMENTS section above.

Reviewed By:

Date:

OS/CRS Salem Common Page 18 of 18 Rev. 0

NC.TQ-WB.ZZ-031 0(Z)

STATION:

SYSTEM:

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SALEM Administrative Section Examination TASK:

TASK NUMBER:

NUMBER:

2002 GOLF NRC RO Al Questions ALTERNATE PATH:

APPLICABILITY:

EO =

RO FW-K/A NUMBER:

IMPORTANCE FACTOR:

See Questions RO SRO STA =

SRO =L EVALUATION SETTING/METHOD:

Room with references

REFERENCES:

See Questions TOOLS AND EQUIPMENT:

None VALIDATED JPM COMPLETION TIME:

TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS:

APPROVAL:

BARGAINING UNIT REPRESENTATIVE TRAINING SUPERVISOR or designee OPERATIOI:S/MANA) ER ord dsigneef CAUTION:

No plant equipment shall be operated during the performance of a JPM without the following:

1. Permission from the OS or Unit CRS;

2. Direct oversight by a qualified individual (determined by the individual granting permission based on plant conditions).

3. Verification of the "as left" condition by a qualified individual.

ACTUAL JPM COMPLETION TIME:

Minutes ACTUAL TIME CRITICAL COMPLETION:

Minutes JPM PERFORMED BY:

GRADE: FISAT

] UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE:

DATE:

Nuclear Common N/A N/A

'0Z ý4 Page I of 5 Rev. 0

GOLF GROUP NRC EXAMINATION ADMINISTRATIVE SECTION A.1 REACTOR OPERATOR:

QUESTION #2 (2.1.1)

QUESTION:

You were on loan to the procedures group and stood no watches from June 15 through October 10. Tonight is your first night back with your regular shift.

What requirements must be met before you can assume licensed duties?

ANSWER:

Stand minimum of 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of shift functions under the direction of an Operator; including guided plant tours and supervised shift turnover, all documented on Form SH.OP-DD.ZZ-0067-5.* In addition, supervision must complete Form SH.OP-DD.ZZ-0067-7.

General compliance with Underline* required for SAT

REFERENCE:

SH.OP-DD.ZZ-0067, Personnel Qualification and Training, Rev. 1, Page 16 of 31, B. and F.

Nuclear Common Page 3 of 5

SH.OP-DD.ZZ-0067(,

B.

Actively performing the function of a Reactor Operator (NCO) or Senior Reactor Operator (SRO), means that an individual carries out and is responsible for the duties of a position oi the shift that requires a license as identified in the Technical Specifications. For an SRO.

this is accomplished in the OS or Unit CRS positions. For an NCO, this is accomplished in one of the two NCO positions. To satisfy the performance requirements, completion of a minimum five 12-hour shifts per calendar quarter is necessary. Those licensed operators nc assigned to a shift crew but are actively performing license functions, should document thei watch standing using FORM SH.OP-DD.ZZ-0067-5, Licensed Operator/Shift Technical Advisor/Nuclear Equipment Operator Watch Standing Documentation. Watch standing requirements shall be met beginning the calendar quarter after the quarter in which the license was issued.

C.

Only active SRO's can supervise refueling activities. If they are not active, they must stand one 12-hour shift under direction from an active licensed SRO before performing SRO duties limited to fuel handling. The SRO should document this using FORM SH.OP DD.ZZ-0067-5.

D.

If a licensee has not been actively performing the function of an NCO or SRO, (as defined i1 Section 5.6.1.B), then his/her license is considered inactive. The licensee shall not replace any Technical Specification minimum RO or SRO position of the on-duty operating crew until the provisions of Section 5.6.1 and 5.7 are met.

E.

If an SRO licensed individual does not perform the function of an SRO but does perform the function of a RO during a calendar quarter such that the requirements of 5.6.2 are met only for Operator functions, then the license should be considered active for RO functions but inactive for SRO functions. This status is based on the current operations shift assignments and Operations Department logs. The actions of Section 5.7 shall be performed when necessary to reactivate the SRO function. The operator shall be trained and examined as a SRO.

F.

To reactivate an inactive license, an individual must stand a minimum of 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of shift functions under the direction of an Operator or Senior Operator, as appropriate for the individual's license, within the same calendar quarter. This time must include guided plant tours and supervised shift turnover. It shall be documented using FORM SH.OP-DD.ZZ 0067-5 and SH.OP-DD.ZZ-0067-7, Reactivation Checklist of Previously Inactive Licensed Operators.

G.

The Operations Manager may determine that a training program in conjunction with watch standing is to be used to return the operator to active watch standing status. Such a program should be performance-based and individualized to maximize its effectiveness. Tasks that are not normally selected for requalification training because of a high frequency of performance by active watch standers should be considered for inclusion in this training.

Additionally, Operations line management may decide to assess the performance of an inactive watch stander in either the simulator, the plant, or both before allowing the individual to perform active watch standing duties in other than a training status.

Salem/Hope Creek Rev. I Page 16 of 31

SH.OP-DD.ZZ-0067(Z 5.6.2 Shift Technical Advisors (STA)

A.

Regardless of whether the STA is or is not a Licensed RO or SRO, the STA shall satisfactorily participate in the Licensed Operator Requalification Program. The STA should participate in the requalification training as a member of the operating crew to which the STA is normally assigned.

B.

In accordance with Regulatory Guide 1.8, the STA shall stand three shifts per calendar quarter as the STA. STAs not assigned to a shift crew should document watch standing using FORM SH.OP-DD.ZZ-0067-5.

C.

Shift Technical Advisors who do not perform at least three shifts per quarter as an STA or are not active in STA Continuing Training are considered inactive.

D.

To reactivate a Shift Technical Advisor, an individual shall:

" Receive training sufficient to ensure that the STA is cognizant of facility and procedure changes that occurred during the absence, OR the STA is currently participating in annual requalification training,

"* Complete a dynamic simulator evaluation in the STA position(if not performed during the current or previous year)

"* Stand two watches under the direction of a qualified STA E.

Document the completion of the requirements to reactivate an STA on FORM SH.OP DD.ZZ-0067-6, Reactivation of an Inactive Shift Technical Advisor.

5.6.3 Nuclear Equipment Operator (NEO)

A.

All Nuclear Equipment Operators shall be actively enrolled in the NEO Continuing Training Program. Enrollment and satisfactory participation in the Continuing Training Program are required to maintain proficiency in their qualified Watch stations.

B.

To maintain Building Watch Qualifications, the individual shall stand one 12-hour shift as the Building Watch semi-annually (per calendar year). NEO building Watches for Hope Creek - Reactor, Auxiliary, Turbine and Yard. NEO building Watches for Salem - Primary, Secondary, and Circ/Service Water Operator. During periods when the unit is in shutdown and building watches are combined (Hope Creek ONLY), credit can be taken for standing both buildings in the same watch.

C.

To regain building watch proficiency for an individual actively enrolled and satisfactory participating in the NEO Continuing Training Program, the individual shall stand 1, 12-hour watch under instruction with a currently qualified watch stander on each watch station on each watch station for which proficiency is to be regained. Document the watches using FORM SH.OP-DD.ZZ-0067-5.

Salem/Hope Creek Rev. I Page 17 of 31

GOLF GROUP NRC EXAMINATION ADMINISTRATIVE SECTION A.1 -

"E REACTOR OPERATOR:

QUESTION #1 (2.1.3)

QUESTION:

Unit 1 is at 100% power. You are returning to work after being on vacation for two weeks (a total of 14 days off) and will be assuming the 0700-1900 Unit 1 PO watch.

What are your pre-turnover, turnover, and post-turnover log review requirements?

ANSWER:

Pre-turnover - prior 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s*

Turnover -Control Room Narrative*, red-circled readings*, TSAS Log, Tmod Log (changes only)

Post-turnover - prior 5 days* (unless already transmitted for archiving)

Underline

• required for SAT

REFERENCE:

SH.OP-AP.ZZ-0107, Shift Turnover Responsibilities, Rev.2, Step 5.3.1 and Attachment 14 Nuclear Common Page 2 of 5

SH.OP-AP.ZZ-0107(Q) 3.9 The Operations Superintendent, until properly relieved, shall remain in the control room at all times during accident situations to direct the activities of the control room operators.

[CD-418Y, CD-147Y]

3.10 (Salem) The Information Systems Department is responsible for modifying the shift turnover database (SOTOC) whenever the shift turnover forms are modified.

4.0 PROCESS DESCRIPTION This procedure gives detailed guidelines to be utilized by shift personnel during shift relief to ensure a complete and proper turnover of information and equipment pertaining to their operating stations. The turnover should consist of, at a minimum, appropriate log/document reviews, oral briefings, and completion of applicable checklists.

5.0 PROCEDURE 5.1 Shift/Individual Relief and Turnover

[CD-206C]

5.1.1 Turnover is the presentation of plant-related information by the off-going operator to the oncoming operator. The turnover can take place any time prior to relief, as long as it does not interfere with the off-going operators' ability to perform their assigned duties.

Turnover is to consist of the following as a minimum: [CD-825B]

Log reviews (narratives and red-circled items)

Oral briefing Special Instructions Assurance that critical plant parameters are within allowable limits (parameters and allowable limits shall be described on the checklist, e. g.

out of spec readings on NEO and RO/PO Logs, etc.). [CD-421Y]

Assurance of the availability and proper alignment of all systems essential to the prevention and mitigation of operational transients and accidents (e.g. by a check of the Main Control Boards, surveillance logs, etc.). [CD-421Y, CD-408A]

Identification of systems and components that are in a degraded mode of operation permitted by the Technical Specifications. [CD-421Y]

5.1.2 The plant should be in a STABLE CONDITION before beginning the shift turnover process. [CD-217B]

Salem/Hope Creek Page 4 of 56 Rev,. 2

SH.OP-AP.ZZ-0107(Q) 5.1.3 When turnover must occur during non-stable conditions, one off-going RO/PO should maintain responsibility for monitoring the control boards while the other shift crew members turn over their watches. Once an oncoming RO/PO has completed the turnover, that oncoming RO/PO should then assume responsibility for monitoring the control boards while the last off-going RO/PO turns over the watch.

5.2 Off-going Shift Personnel 5.2.1 Prior to shift relief, the off-going personnel should give an oral briefing to their watch station relief by discussing important items affecting plant operation. This should include the condition, status, and steps of any procedure or surveillance in progress.

5.2.2 Each off-going operator should prepare a listing highlighting planned evolutions, comments, equipment abnormalities, and other items affecting plant operations to aid in the turnover. The appropriate attachment should be used to document this information.

5.2.3 (Hope Creek only) At the end of each shift, the RO/PO should audit the placement of the keys for keylock control switches on Panels 10C650, 10C651, 1AC633, 1BC633, and 1 0C607. These keys are individually labeled according to their own unique control switch function and are normally removed from their respective keylock switches during operation. The Rx Mode Switch and the Scram Discharge Volume Hi Level Scram Bypass Switch must be inserted into their keylock switches. The 4 RPS Channel Switches must be inserted into their keylock switches. The remaining keys must be affixed to the control room panels with magnetic strips. The RO/PO should report any problems to the CRS and should make note of the completed audit on Attachment 6, Equipment Status Checklist.

(Hope Creek only) [CD-105A, CD-239X, CD-359X, CD-379X, CD-639X]

5.3 Oncoming Shift Personnel 5.3.1 Prior to assuming the shift, the oncoming individuals should review various logs which pertain to the assigned watch stations. The review prior to watch assumption should include material generated since the last time on shift or within the past 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, whichever is shorter. Except as noted below, the balance of unreviewed material generated within the previous 5 days should be reviewed after turnover is complete. Material not available in the Control Room due to previous transmittal need not be retrieved for review.

Available unexpired operational Night Orders generated since the individual's last time on shift should be reviewed.

Salem/Hope Creek Rev. 2 Page 5 of 56

SH.OP-AP.ZZ-0107(Q) 5.3.2 Control Board Walk-Downs All oncoming licensed operators (except the OS as described below) should WALK DOWN the control boards under their cognizance with the off-going operator verifying checklist items. Discussions should include, but are not limited to:

Status of safety-related systems [CD-787D]

Running equipment and train alignments Inoperable equipment and Limiting Conditions for Operations, including surveillance requirements Reasons for annunciator alarms Tagged equipment including any surveillance or equipment work in progress at time of shift relief Unusual occurrences during the last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 5.3.3 The oncoming OS should walk-down the control room boards within four hours following the turnover.

Salem/Hope Creek Page 6 of 56 Rev. 2

SH.OP-AP.ZZ-0107(Q)

ATTACHMENT 14 (Page 1 of 1)

DATE

_/

/

SHIFT (Check one) 0 0700-1900 0

1900-0700 SALEM - UNIT 1 REACTOR/PLANT OPERATOR TURNOVER CHECKLIST Page 1 of DOCUMENT REVIEW Initials Control Room Narrative Logs Control Room Operating Log (out of specification readings only)

Aux. Alarm Summary (unexplained alarms only)

Technical Specification Action Statement Log Temporary Modification Log (Changes Only)

Shutdown Safety Assessment Checklist (Attachment 27)

OPERATING STATUS Mode Radioactive Gas Reactor Power Release in Progress Gross MWe Liquid Release RCS Boron In Progress Safety System Status Safety System Status Basis Initials CONTROL BOARD WALKDOWN (Including OHA / Panels / Lamps)

1.

ABNORMAL SYSTEM OPERATIONS and/or ALIGNMENTS)

2.

MAJOR EVOLUTIONS / WORK ACTIVITIES IN PROGRESS (From CRS)

3.

MAJOR EVOLUTIONS / WORK ACTIVITIES COMPLETED LAST SHIFT (From CRS)

Date Oncoming Reactor Operator Date Salemn/Hope Creek Off-going Reactor Operator Page 36 of 56 Rev. 2

GOLF GROUP NRC EXAMINATION ADMINISTRATIVE SECTION A.1 - CANDIDATE COP REACTOR OPERATOR:

QUESTION:

Unit 1 is at 100% power. You are returning to work after being on vacation for two weeks (a total of 14 days off) and will be assuming the 0700-1900 Unit 1 PO watch.

What are your pre-turnover, turnover, and post-turnover log review requirements?

Nuclear Common Page 4 of 5

GOLF GROUP NRC EXAMINATION ADMINISTRATIVE SECTION A.1 -ICANDIDATE COPY1 REACTOR OPERATOR:

QUESTION:

You were on loan to the procedures group and stood no watches from June 15 through October 10. Tonight is your first night back with your regular shift.

What requirements must be met before you can assume licensed duties?

Nuclear Common Page 5 of 5

STATION:

SYSTEM:

TASK:

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SALEM Administrative Section Examination Clear and tag an MOV using Manual Tagging TASK NUMBER:

JPM NUMBER:

1145370104 2002 GOLF NRC RO A2 ALTERNATE PATH:

APPLICABILITY:

EO --

ROW KIA NUMBER:

IMPORTANCE FACTOR:

STA =

SROr-X EVALUATION SETTING/METHOD:

REFERENCES:

NC.NA-AP.ZZ-0005, Rev. 11 SH.OP-AP.ZZ-0015, Rev. 11 TOOLS AND EQUIPMENT:

VALIDATED JPM COMPLETION TIME:

18 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS:

N/A APPROVAL:

BARGAINING UNIT REPRESENTATIVE TRAINING SUPERVISOR or designee OPERATIOI'MANAGER or designee CAUTION:

No plant equipment shall be operated during the performance of a JPM without the following:

1. Permission from the OS or Unit CRS;

2. Direct oversight by a qualified individual (determined by the individual granting permission based on plant conditions).

3. Verification of the "as left" condition by a qualified individual.

ACTUAL JPM COMPLETION TIME:

Minutes ACTUAL TIME CRITICAL COMPLETION:

Minutes JPM PERFORMED BY:

GRADE: F SAT D UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE:

DATE:

2.2.13 3.6 RO 3.8 SRO NC.TQ-WB.ZZ-0310(Z)

&164ZU1. 14, 1W460t4 Nuclear Common Pagel1 of 8 Rev. 0

OPERATOR TRAINING PROGRA JOB PERFORMANCE MEASURE NAME:

DATE:

NC.TQ-WB.ZZ-0310(Z)

SYSTEM:

TASK:

Administrative Select the blocking points for tagging MOV 2SJ1 with SAP out of service.

TASK NUMBER:

1145370104 INITIAL CONDITIONS:

1.

Unit 2 is in Mode 1.

2.

SAP/WCM is out of service

3.

2SJ1 failed to close after it was inadvertently opened.

4.

The Operations Manager has authorized Manual Tagging for the 2SJ1.

NOTE: Need an "Examination Tagging Package" for this JPM INITIATING CUE:

Prepare a blocking point list for valve repairs using Manual Tagging lAW SH.OP NA.ZZ-0015. Work is to be performed on 2SJ1 valve motor operator only.

Nuclear Common Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Page 2 of 8 Rev. 0

NC.TQ-WB.ZZ-031 0(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM:

Administrative Clear, tag and manually close an MOV NAME:

DATE:

STEP STEP COMMENTS NO.

(*Denotes a Critical Step)

STANDARD EVAL (Required for

(#Denotes a Sequential Step)

S/U UNSAT evaluation)

START TIME:

1 Candidate reviews NC.NA-AP.ZZ-0015.

Locates and reviews Section 5.8, MANUAL and/or SH.OP-AP.ZZ-0015 for manual TAGGING, of SH.OP-AP.ZZ-0015.

tagging instructions.

5.8.1, Notifies all Clearing Agents to report to CUE: All Clearing Agents have reported to Step 1 WCC WCC..

Establishes a Manual Tagging File in CUE: Manual Tagging File has been WCC established.

Maintains all existing WCD's and Manual CUE: All WCD's are being maintained.

WCD's in the Manual Tagging File.

Initiates new Manual Tagging Index, CUE: Manual Tagging Index has been Form 6 and sequentially numbers new initiated at Work Control Center and is manually created WCD's beginning with maintained there, this will be WCD 'M001".

number 'MO01'.

Refers to Manual Tagging file AND last CUE: Off-normal Position Reports have generated Off-normal Position Reports.

been generated and reviewed. No information impacts this WCD.

Performs tagging operations as directed Locates and reviews Section 5.1, WCD in appropriate sections of procedure.

INITIATION, of the procedure.

5.1.1 Evaluates Order, Notification, Equipment CUE: Tagging is required.

Restriction or Procedure Requirement for Step 1 Required Tagging 5.1.1 If Tagging is not required exit procedure Does not exit procedure.

Step 2 TASK:

Nuclear Common Page 3 of 8 Rev. 0

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NC.TQ-WB.ZZ-031 0(Z)

NAME:

DATE:

SYSTEM:

Administrative TASK:

Clear, tag and manually close an MOV STEP STEP COMMENTS NO.

(*Denotes a Critical Step)

STANDARD EVAL (Required for

(#Denotes a Sequential Step)

S/U UNSAT evaluation) 5.1.1 Apply the following for non-station Tagging is on station equipment, does not Step tagging evolutions.........

apply Step 5.3 5.1.2 Determine Blocking Points and Tag Reviews section 5.1.2 Types 5.1.2 Review the following Reviews items in Step 1 Step 1 Scheduled activities for system or CUE: 2SJ1 Motor Operator is to be component to be tagged repaired.

Work performed from SAP Orders Determines SAP is not in service Notifications Determines SAP is not in service Procedure requirements.

Determines there are no Procedure Requirements Controlled Documents and Drawings CUE: Use Controlled Documents and from TDR or DCRMS.

Drawings in the room Locates Drawing in classroom Locates Drawing 222485, 2C WEST VALVES & MISC. 230V. VITAL CONTR.

CTR. ONE LINE Provide Candidate with copy of drawing.

Main Control Room Drawings for CUE: There are no changes on drawings changes Uncontrolled Documents and Drawings CUE: No uncontrolled Documents and Drawings are to be used Page 4 of 8 Nuclear Common Rev. 0

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM:

Administrative TASK:

Clear, tag and nanually close an MOV STEP STEP COMMENTS NO.

(*Denotes a Critical Step)

STANDARD EVAL (Required for

(#Denotes a Sequential Step)

S/U UNSAT evaluation)

Historical, Standard or Template WCD's Determines SAP is not in service 5.1.2 Performs the following Performs items in Step 2 Step 2 For ESO switching orders,...............

Determines there are no ESO switching orders Resolve Technical and Work Scope CUE: There are no problems problems If any of the following components will be Determines a Motor Operated Valve is to used as blocking points.........

be worked and locates MOV rules on page 2 of Attachment 2 Also determines a Bezel and Control Room Control is affected and locates bezel rules on page 13 of Attachment 2 Refer to Attachment 3 for rules on tag Determines Red Blocking Tags are types required for WCD on Pagel of Attachment 3

Select blocking points and tag types Determines that breaker 2SJ1-MTRY (from NOTE: After Drawing 222485), and 2SJ1 bezel control Candidate locates need Red Blocking Tags applied. May drawing, Examiner determine valve handwheel will have Red will provide a copy Blocking Tag though this is not critical to for student to mark task.

up.

NOTE-Candidate may elect to use "TRIS" identifier 2CY2AX2A for breaker, this information is in a table on the drawing NC.TQ-WB.ZZ-0310(Z)

NAME:

DATE:

Nuclear Common Page 5 of 8 Rev. 0

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Clear, tag and manually close an MOV Nuclear Common SYSTEM:

Administrative TASK:

NC.TQ-WB.ZZ-0310(Z)

NAME:

DATE:

STEP STEP COMMENTS NO.

(*Denotes a Critical Step)

STANDARD EVAL (Required for

(#Denotes a Sequential Step)

S/U UNSAT evaluation)

Ensure blocking points will not adversely Determines there are no air isolations impact other systems or components.

(i.e., air isolations)

Ensure equipment within the tagging Determines blocking points will adequately boundary is protected from damage due afford protection to inadvertent operation.

5.1.3 Create Tagging Package Reviews Section 5.1.3 5.1.3 Perform the following Performs steps Step 1 Mark up Drawings and Documents, Marks up drawing circling the breaker for showing blocking points within the WCD valve 2SJ1.

boundary Page 6 of 8 Rev. 0

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NC.TQ-WB.ZZ-031 0(Z)

NAME:

DATE:

SYSTEM:

Administrative TASK:

Clear, tag and manually close an MOV STEP STEP COMMENTS NO.

(*Denotes a Critical Step)

STANDARD EVAL (Required for

(#Denotes a Sequential Step)

S/U UNSAT evaluation)

Initiate the WCD in SAP, use Forms 1&4 Determines WCM is unavailable, locates if the WCM is unavailable, forms EVALUATOR-Provide forms after Candidate locates them in procedure Candidate fills out appropriate sections of Forms 1 Candidate fills out Form 4 identifying

"* *230V Brkr for 2SJ1 and RBT

"* 2SJ1 Handwheel and RBT (not critical)

"* *2SJ1 Bezel Control and RBT STOP TIME:

Terminating Cue: When the Candidate completes Form 4 state "This JPM is complete".

Nuclear Common Page 7 of 8 Rev. 0

NC.TQ-WB.ZZ-0310(Z)

INITIAL CONDITIONS:

1.

2.

3.

4.

Unit 2 is in Mode 1.

SAP/WCM is out of service.

2SJ1 failed to close after it was inadvertently opened.

The Operations Manager has authorized Manual Tagging for the 2SJ1.

INITIATING CUE:

Prepare a blocking point list for valve repairs using Manual Tagging lAW SH.OP-NA.ZZ-0015.

Work is to be performed on 2SJ1 valve motor operator only.

Nuclear Common Page 8 of 8

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020626 SH.OP-AP.ZZ-0015(Q) 5.8 MANUAL TAGGING 5.8.1 Prepare for/

Recover from Manual Tagging (WCCS)

NOTE Implementation of Manual Tagging requires approval of the Operations Manager or designee and should be kept to a minimum.

In an emergency the on duty OS may authorize manual tagging required to move the plant to a safer condition without the approval of the Operations Manager.

5.8.2 Create Manual Tags (WCo

• 1"

1. IF the WCM becomes unavailable, THEN perform the following:

"o Notify all Clearing Agents to report to the WCC to manually sign on all active WCDs under which they are performing work.

"o Establish a Manual Tagging File in the WCC.

"o Maintain all existing WCDs that are being modified in any way AND all manually created WCDs in the Manual Tagging File until WCM is available and updated.

"o Initiate a new Manual Tagging Index, Form 6, for the Manual Tagging File, sequentially number new manually created WCDs beginning with the WCD number 'M001'.

" Refer to the Manual Tagging file AND the last generated Off Normal Position Reports for configuration control information.

"o Perform tagging operations as directed in the appropriate sections of this procedure.

2. WHEN the WCM becomes available, THEN, perform the following:

o Enter all outstanding transactions into the WCM.

o Replace the manual created WCDs with electronically generated WCDs.

a Generate a new Off-Normal Position Report AND compare to the last generated report; resolve all discrepancies.

o Retain all manually generated tagging paperwork with electronically generated WCD packages.

o IF the WCM is unavailable, THEN hand write blocking tag information on a blank tag sticker in the following format:

Unit WCD #

Blocking Point Description Position Tagged For L

Salem/Hope Creek Page 34 of 67 Rev 11

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020626 SILOP-AP.ZZ-0ols(Q) 5.0 PROCEDURE

• Reference to (Note) throughout this procedure indicates that detailed instructions and SAP manipulations are available in the SH.WM-DG.ZZ-0015, Work Clearance Management Desk Guide 5.1 WCD INITIATION 5.1.1

• Perform the following:

Evaluate for Required Tagging

1. Evaluate Order, Notification, Equipment Restriction, or Procedure (Initiator)

Requirement for Required Tagging using.

2. IF Tagging is NOT required, THEN EXIT this procedure.

3. Apply the following for tagging evolutions on non-station equipment located outside the protected areas of Salem and Hope Creek:

"* These tagging evolutions are conducted using the Manual Tagging method when WCM identifiers and station labeling do not support the use of WCM for tag preparation.

"* The Hope Creek WCC will maintain a non-station tagging file (containing both WCM and Manual tagouts) and an index for non-station tagging done using the Manual Tagging method.

Manual tagout numbers will be issued in the YY-XXX format with YY being the year (2001 =01) and XXX being a sequential number.

"* Fire Protection shall prepare the tagout for Manual non-station tags, or obtain assistance from the WCC for non-station tagging that can be accomplished using WCM.

"* Fire Protection supervisor shall be the approving and authorizing supervisor for non-station tagging.

"* Non-station tagouts shall be logged at the WCC prior to implementation, filed at the WCC during use, and logged off at the WCC upon release.

"* Fire Protection Operators are Qualified Operators for all non station tagging.

"* All blocking points used for non-station tagging shall be evaluated by the Fire Protection supervisor and the WCC supervisor for labeling and inclusion in the WCM.

Salem/Hope Creek Page 9 of 67 Rev 11

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020626 SH.OP-AP.Z=Z_015(Q) 5.1.2 Determine BlockingPoints and Tag Types (Initiator)

NOTE Detailed instructions and SAP manipulations are available in SH.WM-DG.ZZ-O01 5, Work Clearance Management Desk Guide.

1. Review the following:

"o Scheduled activities for the system or component to be tagged.

"o Work to be performed from SAP Orders (Note)

"o Notifications (must be converted to a SAP order IAW NC.WM-AP.ZZ-000l (Q)).

"o Procedure Requirements "o Controlled Documents and Drawings from the TDR or DCRMS (Note)

"o Main Control Room Drawings for any outstanding Drawing Changes "o Uncontrolled Documents and Drawings that have received an independent field verification "o Historical, Standard, or Template WCDs for system or component to be tagged (Note)

2. Perform the following:

oi For ESO switching orders, translate switching order designators to the corresponding WCM blocking point designators.

"o Resolve Technical and Work Scope problems with:

"* Scheduler

"* Planner

"* Implementing Shops

"* WCCSs "o IF any of the following components will be used as blocking points, OR will be worked on inside the tagging boundary, THEN Refer to Attachment 2 for rules:

"* Vents and Drains

"* Grinnell-Saunders Diaphragm Valves

"* Repacking Valves on the Backseat

"* Motor Operated Valves

"* Air Operated Valves and Dampers

"* Blank Flanges

"* Freeze Seals

"* Electrical Disconnects, Grounds, Equipment w/ YPTs, Breakers, Cubicles, Handswitches, Control Circuits

"* Fuses

"* Bailey Fuses

"* Bezels and Control Room/Remote Shutdown Panel Controls a Refer to Attachment 3 for rules on tag types.

"o Select blocking points and tag types.

"o Ensure selected blocking points will not adversely impact other systems or components. (i.e., air isolations)

"o Ensure equipment within the tagging boundary is protected from damage due to inadvertent operation.

Salem/Hope Creek I

Page 10 of 67 Rev 11

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020626

.1.3 Create Tagging Package (Initiator)

NOTE Detailed instructions and SAP manipulations are available in SH.WM-DG.ZZ-O015, Work Clearance Management Desk Guide.

1.

bH.OP-APzM-o15(Q)

Perform the following:

"o Mark-up Drawings and Documents: (Note)

"* Show blocking points, vent paths, and section of the system within the WCD boundary

"* For system outages, identify order numbers for components to be worked on the drawings

" Initiate the WCD in SAP ((Note), use Forms I & 4 if the WCM is unavailable):

"* Refer to Attachment 4 for rules/guidance on the following:

"> Temporary Blocking Points

" Long Text and Special Instructions

" Sequencing blocking points

"" For ESO WCDs, include the ESO switching order number in the WCD header text

"* Identify required Discipline Reviews for the following

((Note), list on Form I if the WCM is unavailable):

") Logic circuits, control circuits, or complex electrical blocking points less than 480V

", Bailey blocking points

")' Blocking points under the jurisdiction of another Department (i.e., fire protection, chemistry, Radwaste)

")' Blocking points with the potential to cause a valid ESF initiation/actuation Permit WCD to the orders ((Note), list on Form 5 if the WCM is unavailable).

"o Perform final verification that the WCD provides adequate isolation for the given job.

"o Assemble the Tagging Package (drawin.s, documents, list of orders, WCD header page, and tagging list, ESO switching orders).

"o Forward the tagging package or WCD information for the following:

"* Qualified Operator field verification

"* Discipline Reviews

"* Review and pre-approval by an Approving Supervisor Salem/Hope Creek Page I1I of 67 Rev 11

ALL ACTIVE ON-THE-SPOT CHANGES MUST 20020626 BE ATTACHED FOR FIELD USE SHLOP-AP.ZZ-O 15(Q)

ATTACHMENT 2 COMPONENT TAGGING RULES (Page 13 of 13)

BEZETLS AND CONTROL ROOM/REMOTE SHUTDOWN PANEL CONTROLS (970103114)

NOTE A bezel RBT shall not be used as the sole isolation if a personnel or equipment hazard can exist due to energized sources.

" Control Room and Remote Shutdown Panel controls shall be considered remote operators and shall be tagged with the appropriate 'safety tag' (RBT, WBT, YPT, or WCT) whenever that control station will remain operational or become operational while the field tags relating to that component are in place.

"* IF ALARA conditions prohibit the tagging of MOV handwheels, THEN a RBT should be placed on the remote operator for the MOV that denotes the required position for the WCD.

"* WHEN equipment is tagged and the associated Control Room or Remote Shutdown Panel control is not, and will not become operational (application of 'safety tag' not required per the above rule),

THEN the NCO shall install a bezel block and annotate the WCD

'Untagging Text' to ensure removal upon release of the WCD. An "INF" type tag may be used to track application of the bezel block.

"* Bezel Stations that are tagged may be removed from the Control Console for the purpose of checking proper indication/bulbs (with OS/CRS permission), provided the tagged position is verified when the bezel station is reinstalled.

" Bezel and Control Room/Remote Shutdown Panel Control RBTs may be used as the sole isolation point when establishing a TEST BOUNDARY.

" IF a bezel block is used, THEN it will be attached in such a manner as not to obstruct the view of other components on the bezel.

Salem/Hope Creek Page50 of 67 Rev 11

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020626 SH.OP-AP.ZZ-0015(Q)

ATTACHMENT 2 COMPONENT TAGGING RULES (Page 2 of 13)

MOTOR OPERATED e

WHEN an MOV is used as a mechanical blocking point, VALVES (MOV)

THEN a RBT shall be placed on both the associated MOV breaker and on the MOV maniial handwheel.

" Restrictive ALARA conditions may prohibit the tagging of MOV handwheels. Determination of these conditions shall be made jointly by the OS/CRS, Clearing Agent, Job Technician, and the on-duty Radiation Protection Technician.

"* IF ALARA conditions prohibit the tagging of MOV handwheels, THEN a RBT shall be placed on the remote operator and breaker for the MOV that denotes the required position for the WCD.

MOVs shall be verified in the proper position per the WCD prior to tagging.

• WHEN an MOV is manually seated or backseaied, THEN administrative controls shall be used to ensure the valve is manually unseated prior to stroking the valve electrically. (refer to NC.NA-AP.ZZ-0005(Q) for additional guidance)

• Prior to working on the motor operator of an MOV, that has a RBT on the handwheel, an Engineer or Clearing Agent (trained on MOVs) must evaluate the work to ensure the valve position will not change fiom the tagged position. The following rules apply:

") Engineer or Clearing Agent doing the work will review valve design.

" IF there is any chance the MOV will change position, AND the work must be completed, THEN an alternate means of maintaining the valve in the closed position will be installed and tagged.

> The Clearing Agent doing the work, the Engineer and the Tagging Authority, will agree upon the method of maintaining valve position.

> The clutch shall not be operated.

>' The Engineer and/or Clearing Agent will enter all relevant information including engineer's name in the long text of the associated WCD.

> The Clearing Agent will document a discipline review of the associated WCD.

Salem/Hope Creek Page 39 of 67 Rev 11

2SJI R. W. S. T. TO CHARGING PUMPS STOP VALVE 2SJ1-MTRY 2CS17 -

SPRAY ADDITIVE TANK DISCHARGE VALVE 2CS17-MTRY 22CS2 -

CONTAINMENT SPRAY PUMP DISCHARGE VALVE 22CS2-MTRY 2CV140 -

CHARGING PUMP RECIRC. STOP VALVE 2CV140-MTRY 22SJ33 - SAFETY INJECTION SUCTION VALVE 22SJ33-MTRY 00 oV) 00 (I c N;Jc 0

-r m

_0 f 3C) 0-

-uja:

OUTSTAND!NG CHANGES MUST BE ATTACHED FOR WORKING COPY 2'WG 222485 001 47 Printed 20021028 ANY REVISION TO THIS DRAWING1 ATTENTION" SHALL BE MADE ONLY BY CAEDI SALEM NUCLEAR GENERATING STATION NO. 2 UNIT-AUXILIARY BUILDING 2C WEST VALVES & MISC. 230V. VITAL CONTR. CTR. ONE-LINE DIAGRAM MK. NO. 1-2110 ELECTRICAL PSEG NUCLEAR, L.L.C.

DRAWN K.R. LEWIS

.. CHECKED R.C. H--

SCALE NONE DATE 12-08-86 EXAMINED A THOMSON AUTH N1 APPROVED _R. T. STANLEY 22 24 85 A

10 11 E

3551-18 I

I lz w

CA (A

4 00 ro 0)

A 1779 -4 7 10 11

OUTSTANDING CHANGES MUST BE ATTACHED FOR WORKING COPY DWG 222485 001 47 Printed 20021028 lIfOll.l

&."I1 1 I--

II iA1 FIRST LINE SEON LINE (SEE NOTE 10)

E LINE 2CY2AX1A 2SJ30 - RWST TO S.I. PUMP STOP VALVE 2CY2AXlE 2SJ67 - SAFETY INJECTION PUMP MINIFLOW TO RWST V 2CY2AXII SPARE MMIS NUMBER: 12110 2CY2AXIL INCOMING 2CY2AX2A 2SJ1 - RWST TO CHARGING PUMP STOP VALVE 2CY2AX2E 2CS17 - SPRAY ADDITIVE TANK DISCHARGE VALVE 2CY2AX21 22CS2 - CONTAINMENT SPRAY PUMP DISCHARGE VALVI

OUTSTANDING CHANGES MUST BE ATTACHED FOR WORKING COPY DWG -22485 001 47 Printed 20021028

'6SD TO THE 12C' EAST VALVE CONTROL CENTER.

6. STARTERS SHOWN IN POS. 11, 4E, 71, 8A, 8E, 81, & CIRC. BKR. IN POSE 'D60 ARE TO BE RELOCATED FROM THE '2C" EAST VALVE CONTROL CENTER.

7. DELETED

8. SEE NOTE 06 ON 0WG. #222490-B-9551

9. BUS VOLTAGE LISTED AS 230 VOLTS ARE NOMINAL AND ARE IN FACT 240 VOLTS.

10. THIS IS THE TRIS DATABASE DESIGNATOR.

?AWINGS:

MISC. 230V. VITAL CONTROL CENTER DWG. "222483-A-17; MISC. 230V. VITAL CONTROL CENTER DWG. '222484 -A-17T MISC. 230V. VITAL CONTROL CENTER WIRING DIAG.

DWG. '203712-A-88" UNITS WIRING DIAGRAM DWWO. 220802-A-14ý SYMBOL LIST DWG. 0601658-B-95;1 HTR. ELEMENTS FOR SAFETY RELATED MOV'S CALC. ES-18.006

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020626 SH.OP-AP$ZZ-dOI(Q)

FORM I WORK CLEARANCE DOCUMENT:

ESO NUMBER:

EQUIPMENT UNAVAILABLE/Referenuce object:

COMMENTS:

SPECIAL INSTRUCTONS FOR TAGGING:

L/6 INTIJATED BY:

C1AA.D h/1 T-ý-

DATE:

PRE-APPROVED1 BY:

WCD AUTHORIZED BY:

DATE:

(ON-DUTY OSCRY WCCS)

SPECIAL INSTUCTos FOR RELEASE:

WCD RELEASE APPROVED BY:

DATE:

RELEASED CONFIMED (IF WCM WAS UNAVAILABLE UPON REQUEST)

Salem/Hope Creek Rev 1 Page 60 of 67

FORM 4 TAGGING/UNTAGGING WORK LIST

• /REQUEST 0 RELEASE TYPE (circle one) FULL PARTIAL TEMPORARY SH.OP-AP.ZZ-0015(Q)

DISCIPLINE REVIEWS:

4111/

WORK CLEARANCE DOCUMENT NUMBER:

,Z9 69 /

This Worksheet: Page / of_/

Verified Date/Time Seg 1

1 L ___ I I

I -

• 0 -

I I ________

J.

QO Initials TAGGED BY: CA DATE/TIME:

Salem/Hope Creek I

VERIFIED BY:

'age 63 of 67 K0 >

or or rq 0

z

-'4 DATE/IME:

Rev 11 Initials

-Tagging Point Description

-ý30 V01-7 Uy S 7_4 10 r-OR I

I I

I I

I Identifier jTag T !Sr 7-Current Position x

Desired Position Apply/Release Date/Time

STATION:

SYSTEM:

TASK:

TASK NUMBER:

JPM NUMBER:

ALTERNATE PATH:

APPLICABILITY:

EO =

NC.TQ-WB.ZZ-031 0(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SALEM Administrative Section Examination Perform control room actions for a fuel handling incident in the Fuel Handling Building (FHB) 1140170401 2002 GOLF NRC RO A3 K/A NUMBER:

IMPORTANCE FACTOR:

ROL-STA =-

SRO 2.3.10 2.9 RO 3.3 SRO EVALUATION SETTING/METHOD:

Simulator/Perform or Control Room/Simulate

REFERENCES:

S2.OP-AB.FUEL-0001, Rev. 3 TOOLS AND EQUIPMENT:

NONE VALIDATED JPM COMPLETION TIME:

15 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS:

N/A APPROVAL:

"A41ý BARGAINING UNIT REPRESENTATIVE TRAINING SUPERVISOR or designee OPERATIO N ANAi ER or deglignee CAUTION:

No plant equipment shall be operated during the performance of a JPM without the following:

1. Permission from the OS or Unit CRS;

2. Direct oversight by a qualified individual (determined by the individual granting permission based on plant conditions).

3. Verification of the "as left" condition by a qualified individual.

ACTUAL JPM COMPLETION TIME:

15 Minutes ACTUAL TIME CRITICAL COMPLETION:

N/A JPM PERFORMED BY:

GRADE: []SAT j UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE:

DATE:

'40 ýý Nuclear Common Page 1 of 7 Rev. 0

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

NC.TQ-WB.ZZ-0310(Z)

Fuel Handling Incidents (APE 036)

Perform control room Actions for a fuel handling incident in the Fuel Handling Building (FHB)

TASK NUMBER:

1140170401 INITIAL CONDITIONS:

1.

Core re-load is in progress on Unit 2.

2.

The transfer canal gate valve is open.

3.

The transfer cart is in the Fuel Handling Building (FHB).

4.

There are 8 people in the FHB.

SIMULATOR SETUP:

Any IC with RCS de-pressurized and appropriate equipment running or simulate performance in the Simulator.

INITIATING CUE:

You are the Control Board Operator. A refueling Crew member in the FHB reports that a fuel assembly has been dropped in the transfer canal. Assume that radiation levels are rising in the FHB but are <1 R/hr and no one has been injured.

Implement S2.OP-AB.FUEL-0001, Fuel Handling Incident.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Nuclear Common SYSTEM:

TASK:

Page 2 of 7 Rev. 0

NC.TQ-WB.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM:

Fuel Handling (034)

Perform Control Room actions for a fuel handling incident inthe Fuel Handling Building (FHB)

STEP STEP COMMENTS NO.

(*Denotes a Critical Step)

STANDARD EVAL (Required for

(#Denotes a Sequential Step)

S/U UNSAT evaluation)

START TIME:

Evaluator provides a copy of S2.OP-AB.FUEL-0001.

3.1 Initiate Attachment 1, Continuous Action Summary

a. If at any time radiation levels in the Radiation levels < 1 R/hr as noted in Initial FHB or CNMT reach 1 R/hr then Conditions evacuate all personnel from the affected area.

b. If at any time radiation protection CUE:

No sample results available yet.

airborne sample results indicate iodine activity in CNMT then operate Iodine removal Units as follows - -

3.2 Notify personnel at the scene of the incident to:

"* Stop all fuel transfers in process.

"* Evacuate all non-essential personnel Pages or otherwise contacts FHB and from the scene.

provides specified direction.

CUE:

Acknowledge order.

3.3 Has the incident occurred in the FHB?

Answers YES.

Nuclear Common TASK:

Page 3 of 7 Rev. 0

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Fuel Handling (034)

Perform Control Room actions for a fuel handling incident inthe Fuel Handling Building (FHB)

STEP STEP COMMENTS NO.

(*Denotes a Critical Step)

STANDARD EVAL (Required for

(#Denotes a Sequential Step)

S/U UNSAT evaluation) 3.4 Notify personnel in the FHB to place any Pages or otherwise contacts FHB and fuel assembly being handled into the provides specified direction.

emergency rack X-3 or designated location, whichever takes less time.

CUE:

Acknowledge order.

CUE:

The assembly being handled was the one that dropped.

3.5 PRESS FHB VENTILATION, EXH FLTR Depresses FHB VENTILATION, EXH FLTR TRAINS, HEPA 22 PLUS CHAR TRAINS, HEPA 22 PLUS CHAR pushbutton.

pushbutton* and verifies change in status or verifies already running.

3.6 Ensure the following:

Verifies:

"* All available FH Exhaust Fans are 0 21 and 22 FHB Exhaust Fans I/S running.

"* HEPA 22 PLUS CHAR and 0 HEPA 22 PLUS CHAR and SEQUENCE COMPLETE lights SEQUENCE COMPLETE lights illuminate.

illuminated.

HEPA 21 ONLY and SEQUENCE HEPA 21 ONLY and SEQUENCE COMPLETE lights extinguish.

COMPLETE lights extinguished.

Record time I/S in CUE:

Mark the time to log the SC.OP-AP.ZZ-0004(Q), Cyclic Data information later and continue with Monitoring Program.

the procedure.

Nuclear Common SYSTEM:

TASK:

NC.TQ-WB.ZZ-031 0(Z)

NAME:

DATE:

Page 4 of 7 Rev. 0

NC.TQ-WB.ZZ-031 0(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM:

Fuel Handling (034)

TASK:

Perform Control Room actions for a fuel handling incident inthe Fuel Handling Building (FHB)

STEP STEP COMMENTS NO.

(*Denotes a Critical Step)

STANDARD EVAL (Required for

(#Denotes a Sequential Step)

S/U UNSAT evaluation) 3.12 Notify Radiation Protection of the Contracts RP to provide as much following:

information as is available and directs a survey and sample of the FHB.

"* Location of the incident

"* Details of the incident

"* Affected personnel, if any

"* Survey the area to determine radiological conditions

"* Sample the area for airborne activity CUE:

Acknowledge order.

and contamination 3.13 If fuel transfer cart is in the FHB or Fuel May contact both FHB and CNMT and Transfer Canal, then return the fuel

[direct return of the Fuel Transfer Cart to transfer cart to CNMT.

the CNMTI*.

CUE:

Acknowledge order.

CUE:

Fuel Transfer Cart has been moved to the CNMT.

3.14 If the fuel transfer canal gate valve is Contacts FHB and directs NEO to close open, then close the valve to isolate the gate valve.

Spent Fuel Pool from CNMT.

CUE:

Acknowledge order.

Nuclear Common Page 5 of 7 Rev. 0

NC.TQ-WB.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM:

Fuel Handling (034)

Perform Control Room actions for a fuel handling incident inthe Fuel Handling Building (FHB)

STEP STEP COMMENTS

(*Denotes a Critical Step)

EVAL (Required for NO.

(#Denotes a Sequential Step)

STANDARD S/U UNSAT evaluation) 3.15 Notify all personnel at the scene of the Pages or otherwise contacts FHB and incident to perform the following:

provides specified directions.

Evacuate the affected area CUE:

Acknowledge order. The NEO will evacuate as soon as the gate valve is closed.

Close all doors upon exiting Report to the Control Point Terminate JPM STOP TIME:

Terminating Cue: Repeat back message from the operator on the status of the JPM, and then state "This JPM is complete".

Nuclear Common TASK:

Page 6 of 7 Rev. 0

NC.TQ-WB.ZZ-0310(Z)

INITIAL CONDITIONS:

1.

Core re-load is in progress on Unit 2.

2.

The transfer canal gate valve is open.

3.

The transfer cart is in the Fuel Handling Building (FHB).

4.

There are 8 people in the FHB.

INITIATING CUE:

You are the Control Board Operator. A refueling Crew member in the FHB reports that a fuel assembly has been dropped in the transfer canal. Assume that radiation levels are rising in the FHB but are <1 R/hr and no one has been injured. Implement S2.OP AB.FUEL-0001, Fuel Handling Incident.

Nuclear Common Page 7 of 7

NC.TQ-WB.ZZ-031 0(Z)

STATION:

SYSTEM:

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SALEM Administrative Section Examination TASK:

TASK NUMBER:

JPM NUMBER:

2002 GOLF NRC RO A4 Questions ALTERNATE PATH:

APPLICABILITY:

EO =

ROW-I K/A NUMBER:

IMPORTANCE FACTOR:

STA =

SRO =I See Questions RO SRO EVALUATION SETTING/METHOD:

Room with references

REFERENCES:

See questions TOOLS AND EQUIPMENT:

None VALIDATED JPM COMPLETION TIME:

N/A TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS:

APPROVAL:

BARGAINING UNIT REPRESENTATIVE CW673/444 /t or designee or designee CAUTION:

No plant equipment shall be operated during the performance of a JPM without the following:

1. Permission from the OS or Unit CRS;

2. Direct oversight by a qualified individual (determined by the individual granting permission based on plant conditions).

3. Verification of the "as left" condition by a qualified individual.

ACTUAL JPM COMPLETION TIME:

Minutes ACTUAL TIME CRITICAL COMPLETION:

JPM PERFORMED BY:

Minutes GRADE: F SAT n UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE:___________

Nuclear Common N/A 44 DATE:

Page 1 of 5 Rev. 0

GOLF GROUP NRC EXAMINATION ADMINISTRATIVE SECTION A.4 -

"E REACTOR OPERATOR:

QUESTION #1 (2.4.33)

QUESTION:

Unit 2 is at 100% power. The Emergency Coordinator declared an UNUSUAL EVENT (UE) at 0645 then upgraded to an ALERT at 0710 due to a problem with the Overhead Annunciator System.

What is the latest clock time by which ERDS is required to be activated?

ANSWER:

0810 - ERDS must be activated within 60 minutes after declaration of an ALERT.

REFERENCE:

SALEM ECG, Attachment 8, Secondary Communicator Log, Rev. 7, Step A.3.b Nuclear Common Page 2 of 5

• -~

ECG i *.* "

ATT 8 Pg. I of 9 ATTACHMENT 8 SECONDARY COMMUNICATOR LOG.

Table of Contents Pages 1 - 2 Notifications & Data Collection/Transmission 3 - 4 Incoming Calls (BNE, DEMA. OEM, AAAG, etc.)

5 Major Equipment & Electrical Status (MEES) form 6

Operational Status Board (OSB) form 7 - 8 Station Status Checklist (SSCL) form 9

Common Site UNUSUAL EVENT - Station Status Checklist form Emergency Classification: (circle)

UE ALERT SAE GE Name:

Position: CM2 /TSC2/ EOF2 (Print)

(circle)

A.

NOTIFICATIONS NOTE A new Attachment 8 is required to be implemented if the classification or protective action recommendation (PAR) changes.

Initials

1.

OBTAIN a copy of Attachment 6 and ASSIST Primary Communicator with 15-minute notifications, as necessary..

CM2.TSC2/E

2.

DIRECT the Shift Rad Pro Tech (SRPT) (x2644) to implement SC.EP-EP.ZZ 0301(Q), Shift Radiation Protection Technician Response. (N/A for Common Site).

Name:

Time:

CM2

3.

For an ALERT or hiher emcrecncv:

a.

CALI-0) "1 an additional SRO and have him/her report to the OSC.

Name:

Time:

CM2

b.

ACTIVArII ERDS %%,thin 60 minutes from the Affected Unit's SPDS terminal.

I)

PRESS <U*NIT.MASTER MENU> key.

2)

PR.SS <ERI)S> ke\\

3)

F!LOW sc reen prompt.s CM2 SGS Rev.07

GOLF GROUP NRC EXAMINATION ADMINISTRATIVE SECTION A.4 - KE REACTOR OPERATOR:

QUESTION #2 (2.4.33)

QUESTION:

A SGTR caused a reactor trip and safety injection on Unit 2. The Emergency Coordinator declared a Site Area Emergency. Several minutes ago, Unit 2 SPDS failed.

What is the data transmission requirement with SPDS failed?

ANSWER:

Complete and transmit the Operational Status Board Form every 15 minutes.

REFERENCE:

SALEM ECG, Attachment 8, Secondary Communicator Log, Rev. 7, Step B.2 (from B.3.b)

Nuclear Common Page 3 of 5

ECG ATT 8 Pg. 3 of 9 Initials B.

DATA COLLECTION/TRANSMISSION (cont'd)

2.

IF requested by the TSC, THEN COMPLETE the Operational Status Board (OSB) Form eveyj 15 minutes, (TSS may modify the frequency or data list as appropriate) ; -

( ( ) )

a.

b.

OBTAIN Licensed Operator review.

FAX to Group C.

CM2

3.

ENSURE the Facility OSB and MEES Status Boards are updated as-follows:

) a.

OBTAIN OSB Data from SPDS "Unit Master Menu."

te

) b.

IF SPDS is Out of Service.

THEN REQUEST CM2 to perform step B.2, above. (data set ond frequency of updates may be revised by the TSS based on evemecircumstances)

c.

WHEN significant changes in plant status occur.

THEN REQUEST CM2 to perform step B.1, above.

TSC2/EOF2

4.

WHEN the emergency is terminated.

THEN FORWARD this document and all completed Forms to the-QS (TSS/SSM).

CM2/TSC2/EOF2 C.

INCOMING CALLS STATE OFFICIALS

1.

IF Notifications authority has transferred.

THEN DIRECT the caller to contact the TSC (or EOF if activated)f-,

CM2,TSC2

2.

WHEN contacted by any State Agency Officials (listed here),

DENIA AAA(;

BNE DEP OEM -

Delaware lEmergency Management Agency Delaware Accident Assessment Advisory Group-'!

NJ Bureau of Nuclear EnIgineering in2 NJ I)epartnment ofL-nvironmental Protection NJ Oflice of -mergency Management PERFORM the following

a.

OBTAIN and R[I()RI).

Agenc\\

Caller',, Name Phone #

( )

b.

RIE'A:)

the latest !( Approxed SSCI..

Rev.07 SGS

.]5.*.t

GOLF GROUP NRC EXAMINATION ADMINISTRATIVE SECTION A.4 - ICANDIDATE COPyl REACTOR OPERATOR:

QUESTION:

Unit 2 is at 100% power. The Emergency Coordinator declared an UNUSUAL EVENT (UE) at 0645 then upgraded to an ALERT at 0710 due to a problem with the Overhead Annunciator System.

What is the latest clock time by which ERDS is required to be activated?

Nuclear Common Page 4 of 5

GOLF GROUP NRC EXAMINATION ADMINISTRATIVE SECTION A.4 - CANDIDATE COPYl REACTOR OPERATOR:

QUESTION:

A SGTR caused a reactor trip and safety injection on Unit 2. The Emergency Coordinator declared a Site Area Emergency. Several minutes ago, Unit 2 SPDS failed.

What is the data transmission requirement with SPDS failed?

Nuclear Common Page 5 of 5

NC.TQ-WB.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION:

SALEM SYSTEM:

TASK:

TASK NUMBER:

JPM NUMBER:

Administrative Evaluate a shift staffing situation and take corrective action lAW administrative procedures 1210020302 GOLF NRC - SRO A. 1 ALTERNATE PATH:

APPLICABILITY:

EO =

K/A NUMBER:

IMPORTANCE FACTOR:

RO =

STA =

SRO I--

EVALUATION SETTING/METHOD:

Room with references

REFERENCES:

NC.NA-AP.ZZ-0005 TOOLS AND EQUIPMENT:

None VALIDATED JPM COMPLETION TIME:

12 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS:

APPROVAL:

AJ //f~

BARGAINING UNIT REPRESENTATIVE

-'TRAINI'NGo d Esigne or designee OPE IONS Md iAGER or design e" CAUTION:

No plant equipment shall be operated during the performance of a JPM without the following:

1. Permission from the OS or Unit CRS;

2. Direct oversight by a qualified individual (determined by the individual granting permission based on plant conditions).

3. Verification of the "as left" condition by a qualified individual.

ACTUAL JPM COMPLETION TIME:

Minutes ACTUAL TIME CRITICAL COMPLETION:

N/A JPM PERFORMED BY:

GRADE: D SAT D

UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE:

DATE:

2.1.4 2.3 RO 3.4 SRO N/A Nuclear Common Page I of 5 Rev. 0

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

NC.TQ-WB.ZZ-031 0(Z)

SYSTEM:

TASK:

Administrative Evaluate a shift staffing situation and take corrective action lAW administrative procedures TASK NUMBER:

1210020302 INITIAL CONDITIONS:

1. Both units are at 100% power

2. It is 1500 on Christmas Day

3. You are the Unit 1 CRS

4. The Unit 2 CRS has become ill and must be relieved as soon as possible

5. Other than the watch crew, there is no one on site with an active SRO license

6. The only available, qualified person is the 1900-0700 Unit 1 CRS, Ed Gallagher. Ed has worked five consecutive 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> night shifts. However, he will "stand by", waiting for a call to relieve early.

SIMULATOR SETUP: N/A INITIATING CUE:

Complete the actions required to provide a relief for the Unit 1 CRS.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Nuclear Common NC.TQ-WB.ZZ-0310(Z)

Page 2 of 5 Rev. 0

NC.TQ-WB.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM:

Administrative TASK:

Evaluate a shift staffing situation and take corrective action lAW administrative procedures STEP STEP COMMENTS NO.

(*Denotes a Critical Step)

STANDARD EVAL (Required for UNSAT

(#Denotes a Sequential Step)

S/U evaluation)

START TIME:

1 Locates and reviews "Working Hour Determines that only available relief will Guidelines" in NC.NA-AP.ZZ-0005 exceed 24 working hours in a 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> (Section 5.10) 2and/or Technical period and 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in a seven day period Specifications 2

Locates NC.NA-AP.ZZ-0005 Form-i, CUE: Provide a copy of Form-1 after it is WORKING HOUR GUIDELINE located in NC.NA-AP.ZZ-0005 DEVIATION/AUTHORIZATION Completes Form-i:

3 Enter NAME of relief Enters Ed Gallagher 4

Enter CODE Enters Guideline Code 3 and 4 per the Working Hour Guideline Deviation/Authorization Code Table 5

Enter JUSTIFICATION Illness of Unit 1 CRS and unavailability of any other qualified watch relief Page 3 of 6 Nuclear Common Rev. 0

NC.TQ-WB.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM:

Administrative TASK:

Evaluate a shift staffing situation and take corrective action lAW administrative procedures STEP COMMENTS S

STEP

(*Denotes a Critical Step)

EVAL (Required for UNSAT

(#Denotes a Sequential Step)

S/U evaluation) 6 Enter LAST SCHEDULED DAY OFF CUE: Ed's last scheduled day off was 12/19 Enters 12/19 7

Enter NEXT SCHEDULED DAY OFF CUE: Ed's next scheduled day off is 12/27 Enters 12/27 8

Sign, date and print name as Candidate signs, dates and prints his/her REQUESTING SUPERVISOR own name 9

Obtain signature or TELECON approval Locates number and calls or beeps from DEPARTMENT MANAGER Department Manager CUE: Role play the conversation and grant approval via phone call Signs, dates and prints name of Department Manager and notes date and time of the call 10 Obtain signature or TELECON approval Locates number and calls or beeps from DIRECTOR-OPERATIONS Director-Operations CUE: There is no answer Nuclear Common Page 4 of 6 Rev. 0

NC.TQ-WB.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE Evaluate a shift staffing situation and take corrective action lAW administrative procedures NAME:

DATE:

STEP STEP COMMENTS NO.

(*Denotes a Critical Step)

STANDARD EVAL (Required for UNSAT

(#Denotes a Sequential Step)

I S/U evaluation)

Obtain signature or TELECON approval from DIRECTOR-OPERATIONS Candidate indicates he/she would now call Ed Gallagher with approval for exceeding the "Working Hours Guideline" STOP TIME:

Locates number and calls or beeps Vice President-Operations CUE: Role play the conversation and grant approval via phone call Signs, dates and prints name of Vice President-Operations and notes date and time of the call

+

• 4-I TERMINATE JPM

-

+

4 L~~~~~

I__

Terminating Cue: Repeat back message from the operator on the status of the JPM, and then state "This JPM is complete" Nuclear Common SYSTEM:

Administrative TASK:

11 Page 5 of 6 Rev. 0

NC.TQ-WB.ZZ-0310(Z)

INITIAL CONDITIONS:

1. Both units are at 100% power

2. It is 1500 on Christmas Day

3. You are the Unit 1 CRS

4. The Unit 2 CRS has become ill and must be relieved as soon as possible

5. Other than the watch crew, there is no one on site with an active SRO license

6. The only available, qualified person is the 1900-0700 Unit 1 CRS, Ed Gallagher. Ed has worked five consecutive 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> night shifts. However, he will "stand by", waiting for a call to relieve early.

INITIATING CUE:

Complete the actions required to provide a relief for the Unit 1 CRS.

Nuclear Common Page 6 of 6

NC.NA-AP.ZZ-0005(Q)

FORM - I WORKING HOUR GUIDELINE DEVIATION / AUTHORIZATION Working Hour Guideline Deviation / Authorization Code Table Guideline Code Description 1

More than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in a work period 2

More than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period 3

More than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period 4

More than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any seven day period 5

Less than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> off between work periods NAME Code Justification Last Next Scheduled Scheduled Day Off Day Off 111 11-r

~

c S

I,-- I I, -,

-C

/A,?/c27 1-

+

+

4 i

i I

I Requesting Supervisor (sign)

Department Manager (sign)

Director - Operations (sign)

Date Date Date Requesting Supervisor (print)

Department Manager (print)

Director - Operations (print)

NOTE In the event that the Director - Operations is unavailable to provide this approval the "Director - Operations" approval should only be delegated upward to a VP level position.

Nuclear Common Rev. 11 i

i I

Page 49 of 49

NC.NA-AP.ZZ-0005(Q) 5.9 Operatin2 Plant Status

[CD-174A, CD-515A, CD-483F, CD-883X, CD-424Y, CD-418Y]

5.9.1 The Control Room Operator and the OS/CRS shall be aware of all activities affecting plant equipment.

5.9.2 The Control Room Operator and the OS/CRS should be notified of changes in plant status, abnormalities or difficulties encountered in performing assigned tasks that may affect safe operations.

5.9.3 Supervisors are responsible for the performance of all personnel assigned to them who could affect plant safety.

5.10 Working Hour Guidelines

[CD-093D, HC/SA T/S - 6.2.21 5.10.1 Adequate shift coverage shall be maintained without the routine heavy use of overtime.

5.10.2 The expectation is that all personnel will work nominal 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> work weeks while the units are operating.

Continued on next page Nuclear Common Rev. 11 NOTE 5.10 The guidelines established within this section are in place to limit the working hours of those personnel who perform safety related functions (e.g., Licensed Senior Reactor Operators, Licensed Reactor Operators, Radiation Protection Technicians, Equipment Operators, Chemistry Technicians, and Key Maintenance Personnel (See Definition 7.3).

[HCISA TIS - 6.2.2]

The objective of the Working Hour Guidelines are to prevent situations where fatigue could reduce an individual's mental awareness and decision making ability, thereby jeopardizing reactor safety. [CD-419Y, CD-128D]

I Page 11 of 49

NC.NA-AP.ZZ-0005(Q) 5.10, (Continued) 5.10.3 PRIOR TO performance of overtime in excess of the guidelines listed in step 5.10.4, authorization shall be obtained from the Department Manager and the Director - Operations (In the event that the Director - Operations is unavailable to provide this approval the "Director - Operations" approval should only be delegated upward to a VP level position.

Authorization shall be documented on Form - 1, Working Hour Guideline Deviation /

Authorization.

Approvals may be obtained by telecon as follows:

"* Sign for the approval authority

"* Document the statement "per telecon"

"* Record the name of the individual granting approval Record the time and date the approval was received Completed forms should be retained by the initiating department (Time Administrator) and made available for NRC review for a full operating cycle.

5.10.4 In the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance, or major unit modifications, on a temporary basis the following guidelines shall be followed by Licensed Senior Reactor Operators, Licensed Reactor Operators, Radiation Protection Technicians, Equipment Operators, Chemistry Technicians, and Key Maintenance Personnel (See Definition 7.3):

An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight (excluding shift turnover time).

An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any seven day period (all excluding shift turnover time).

A break of at least eight hours should be allowed between work periods (including shift turnover time).

Except during extended shutdown periods,, the use of overtime should be considered on an individual basis and not for the entire staff on shift.

5.10.5 The Director - Operations or designee shall review individual overtime monthly to ensure that excessive hours have not been assigned. [CD-419Y]

Nuclear Common Rev. 11 Page 12 of 49

N(

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION:

SALEM SYSTEM:

Administrative Section Examination TASK:

TASK NUMBER:

NUMBER:

2002 GOLF NRC SRO Al Questions ALTERNATE PATH:

K/A NUMBE IMPORTANCE FACTC APPLICABILITY:

EO RO STA SRO EVALUATION SETTINGIMETHOD:

Room with references

REFERENCES:

See Questions TOOLS AND EQUIPMENT:

None VALIDATED JPM COMPLETION TIME:

N/A TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS:

APPROVAL:

/

"R:

See RR:

RO Questions SRO N/A BARGAINING UNIT REPRESENTATIVE TRAINING SUPERVISOR or designee MANAGnEe or designee ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION:

JPM PERFORMED BY:

REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE:

Minutes Minutes GRADE:

"- SAT [

UNSAT DATE:

No plant equipment shall be operated during the performance of a JPM without the following:

1. Permission from the OS or Unit CRS;

2. Direct oversight by a qualified individual (determined by the individual granting permission based on plant conditions).

3. Verification of the "as left" condition by a qualified individual.

.TQ-WB.ZZ-0310(Z) f JfWf

• W r

I, CAUTION:

GOLF GROUP NRC EXAMINATION ADMINISTRATIVE SECTION A.1 - KE SENIOR REACTOR OPERATOR:

QUESTION #1 (2.1.12)

QUESTION:

Both units are at 100% power when 1 RI1B-1, Control Room Air Intake Radiation Monitor, fails high. The following Control Area Ventilation (CAV) alignment is noted:

11 and 21 EACS Fans are operating

• The Outside Air Intake Dampers on Unit 1 and Unit 2 are closed What Technical Specification Action Statement(s) must be entered?

ANSWER:

Enter the TSAS for the failed radiation monitor on each unit and the TSAS for the failed damper/interlock on Unit 2. The Unit 2 Outside Air Intake Damper should not close on failure of 1 RI B-1.

"* Unit 1 RMS - 3.3.3.1 Action b, Instrument 3, Action 24

"* Unit 2 RMS - 3.3.3.1 Action b, Instrument 3, Action 27

"* Unit 2 CAV - 3.7.6.b, Action e

REFERENCE:

S1 and S2.OP-SO.CAV-0001, Precautions and Limitations step 3.12 Unit 1 and Unit 2 Technical Specifications

GOLF GROUP NRC EXAMINATION ADMINISTRATIVE SECTION A.1 - KEY SENIOR REACTOR OPERATOR:

QUESTION #2 (2.1.23)

You are the Unit 2 CRS for a rod withdrawal reactor startup at MOL. The Estimated Critical Position (ECP) is Control Bank D-135 steps. The ICRR has been predicting an earlier criticality. With rod motion stopped and an ICRR of

.125, the Reactor Engineer on-duty informs you that the plot predicts criticality at Control Bank D-60 steps.

What action is required?

ANSWER:

Permission to continue the startup must be obtained from the Reactor Engineer and the Operations Manager. With D@60 steps, the Predicted Critical Rod Position differs from the ECP by >400 pcm but <500 pcm.

Underlined required for SAT

REFERENCE:

S2.OP-IO.ZZ-0003, Rev. 16, Step 5.3.15.H.3 Figure 4, INTEGRAL ROD WORTH vs. ROD POSITION IN OVERLAP from S2.RE-RA.ZZ-0012, Rev. 59

U' INTEGRAL ROD WORTH (pcm) w 0iii*

5 15 25 35 45 55 65 75 85 95 105 115 125 128 133 143 153 163 173 183 193 203 213 223 225 0

0 0

0 0

N N

N

A (-

VL UN- -HL-ýZ U I U

AiANUL*

MU lI IL

-A I IA L,

U t'

FAILL U.. _

D.,*

- 1028 SI.OP-IO.ZZ-0003(Q) 5.3.15 (continued)

NOTE The 8-Fold Rod Position occurs at the condition when the highest reading source range channel has increased by three doublings OR eight times the initial count rate prior to control bank withdrawal. This position is equivalent to an ICRR value of 0.125.

G.

WITHDRAW Control Banks A, B and C STOPPING at the following hold points to obtain ICRR data:

CBA Fully Withdrawn S

PRIL Position CBB Fully Withdrawn 8-Fold Rod Position H.

When the ICRR value reaches 0.125, DETERMINE the deviation between the Estimated Critical Rod Position (ECP) and Predicted Critical Rod Position (from the ICRR), and take appropriate action:

1.

IF the ICRR plot indicates Predicted Critical Rod Position is below the Zero Power Rod Insertion Limit (RIL),

THEN INITIATE Rapid Boration, INSERT Control Rod Banks AND RECALCULATE the ECP.

2.

IF the ICRR plot indicates Predicted Critical Rod Position differs from the ECP by > 300 pcm but < 400 pcm, THEN CONTINUE the Reactor Startup, AND EVALUATE the post startup data for trend.

3.

IF the ICRR plot indicates Predicted Critical Rod Position differs from the ECP by > 400 pcm but < 500 pcm, THEN OBTAIN permission from the Reactor Engineer and the Operations Manager prior to continuing with the Startup.

(step continued on next page)

Page 23 of 51 Salem 2 Rev. 16

ALL A.I VL UIN--!

VUI U1AINL.L MU*I It" A I I AL.rU r ur r iLLLu u

r 2002108 S2.OP-IO.ZZ-0003(Q) 5.3.15 (continued)

4.

IF the ICRR plot indicates Predicted Critical Rod Position differs from the ECP by > 500 pcm but < 1000 pcm, THEN:

a.

INSERT the Control Rod Banks, AND RECALCULATE the ECP prior to withdrawing Control Rods.

b.

IF the ICRR plot still indicates Predicted Critical Rod Position differs from the ECP by > 500 pcm but < 1000 pcm on the second attempt, THEN OBTAIN permission from the Reactor Engineering Supervisor and the Operations Manager prior to continuing with the Startup.

5.

IF the ICRR plot indicates Predicted Critical Rod Position differs from the ECP by > 1000 pcm, THEN INSERT the Control Rod Banks. The reactor shall NOT be made critical.

I.

WITHDRAW Control Bank D STOPPING at the following hold points to obtain ICRR data:

_*50 step increments 8-Fold Rod Position J.

IF P-6 (Source Range Permissive) green light energizes, as indicated on 2RP4 1/2 IR channels at 101" amps, prior to criticality, THEN:

1.

SELECT one pen of NR-45 to an Intermediate Range channel and the other pen to a Power Range channel.

2.

BLOCK Source Range High Flux Trip by depressing both "BLOCK SOURCE RANGE A" AND "BLOCK SOURCE RANGE B" pushbuttons on console.

3.

ENSURE Source Range Trains A&B TRIP BLOCKED blue light is illuminated on 2RP4 AND OHA E-5, SR DET VOLT TRBL alarms.

Salem 2 Page 24 of 51 Rev. 16

GOLF GROUP NRC EXAMINATION ADMINISTRATIVE SECTION A.1 - CANDIDATE COP SENIOR REACTOR OPERATOR:

QUESTION:

Both units are at 100% power when 1R1 B-1, Control Room Air Intake Radiation Monitor, fails high. The following Control Area Ventilation (CAV) alignment is noted:

11 and 21 EACS Fans are operating The Outside Air Intake Dampers on Unit 1 and Unit 2 are closed What Technical Specification Action Statement(s) must be entered?

GOLF GROUP NRC EXAMINATION ADMINISTRATIVE SECTION A.1 - ICANDIDATE COPY SENIOR REACTOR OPERATOR:

QUESTION:

You are the Unit 2 CRS for a rod withdrawal reactor startup at MOL. The Estimated Critical Position (ECP) is Control Bank D-135 steps. The ICRR has been predicting an earlier criticality. With rod motion stopped and an ICRR of

.125, the Reactor Engineer on-duty informs you that the plot predicts criticality at Control Bank D-60 steps.

What action is required?

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE I-I STATION:

SYSTEM:

SALEM ADMINISTRATIVE Review a completed surveillance procedure for a MDAFW Pump TASK NUMBER:

JPM NUMBER:

ALTERNATE PATH:

APPLICABILITY:

EO --

1230300302 GOLF NRC - SRO A2 RO =

K/A NUMBER:

IMPORTANCE FACTOR:

STA =

SROj-Xj 3.0 RO EVALUATION SETTING/METHOD:

Room with references

REFERENCES:

S2.OP-ST.AF-0001, Rev. 14 S2.RA-ST.AF-0001, Rev. 5 TOOLS AND EQUIPMENT:

None VALIDATED JPM COMPLETION TIME:

12 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS:

APPROVAL:

A)0#

BARGAINING UNIT REPRESENTATIVE 7_TRAINING S PERVISOR or designee OPERATIONS MANAGER or designee CAUTION:

No plant equipment shall be operated during the performance of a JPM without the following:

1. Permission from the OS or Unit CRS;

2. Direct oversight by a qualified individual (determined by the individual granting permission based on plant conditions).

3. Verification of the "as left" condition by a qualified individual.

ACTUAL JPM COMPLETION TIME:

Minutes ACTUAL TIME CRITICAL COMPLETION:

N/A JPM PERFORMED BY:

GRADE: D SAT D] UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE:

DATE:

TASK:

2.2.12 3.4 SRO N/A a- ) 1&14 Nuclear Common Page 1 of 5 Rev. 0

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM:

TASK:

ADMINISTRATIVE Review a completed surveillance procedure for a MDAFW Pump TASK NUMBER:

1230300302 INITIAL CONDITIONS:

1. Unit 2 is sub-critical at 547°F, 2235 PSIG. All shutdown bank control rods are fully withdrawn.

2. S2.OP-ST.AF-0001(Q), INSERVICE TESTING-21 AUXILIARY FEEDWATER PUMP was completed at the end of the previous shift. The procedure has just been submitted to thE control room.

3. 21 AFW Pump has been left in service to provide feed while preparations are in progress for performing S2.OP-ST.AF-0002.

SIMULATOR SETUP: N/A INITIATING CUE:

You are the Unit 2 CRS. Review S2.OP-ST.AF-0001 (Q), INSERVICE TESTING-21 AUXILIAR' FEEDWATER PUMP.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Nuclear Common Page 2 of 5 Rev. 0

NC.TQ-WB.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM:

ADMINISTRATIVE TASK:

Review a completed surveillance procedure for a MDAFW Pump STEP STEP COMMENTS NO.

(*Denotes a Critical Step)

STANDARD EVAL (Required for UNSAT

(#Denotes a Sequential Step)

S/U evaluation)

Evaluator provides a marked up S2.OP STAF-0001 and a copy of the current revision of S2.RA-ST.AF-0001 START TIME:

1 Verifies current revision of the procedure Verifies revision at Examiner's discretion was used for the ST 2

Step 5.3.2 CRS PERFORM the following:

A. Review this procedure with Attachments 1-4 for completeness and accuracy.

3 Checks all PREREQUISITES (2.0) and No errors PRECAUTIONS AND LIMITATIONS (3.0) initialed 4

Checks all PROCEDURE steps (5.0)

Recognizes that Step 5.1.5.should NOT be initialed or properly N/A'd N/A. The Unit is in Mode 3 - TSAS 3.7.1.2 should have been entered. Specifies that a NOTF should be written.

CUE: Assume the NOTF has been written.

Continue reviewing the procedure.

5 Reviews Attachment 1 Verifies all blocks completed, instrument calibration dates are current Nuclear Common Page 3 of 5 Rev. 0

NC.TQ-WB.ZZ-031 0(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE ADMINISTRATIVE Review a completed surveillance procedure for a MDAFW Pump NAME:

DATE:

STEP COMMENTS

(*Denotes a Critical Step)

STANDARD EVAL (Required for UNSAT

(#Denotes a Sequential Step)

S/U evaluation)

Reviews Attachment 2 0 Verifies all blocks completed

"* Compares collected data to S2.RA ST.AF-0001 acceptance criteria

"* Determines Vibration Position 3V is in Alert Range*

Reviews Attachment 3 Notes 23 and 24AF21 are throttled, supplying feed to the SG's Reviews Attachment 4 Reviews Section 1.0 for COMMENTS and 2.0 for SIGNATURES Completes Section 5.3.2 Specifies that 5.3.2.C applies:

"* Pump is operable but in ALERT range

"* Initiate a change to increase test frequency lAW NC.WM-AP.ZZ 0003 CUE: Change is being initiated by another Operator.

10 Complete Attachment 4, Section 3.0 Signs and dates 11 Forwards procedure to STA TERMINA TE JPM STOP TIME:

Terminating Cue: State "This JPM is complete" Nuclear Common SYSTEM:

TASK:

9 Page 4 of 5 Rev. 0

NC.TQ-WB.ZZ-0310(Z)

INITIAL CONDITIONS:

1. Unit 2 is sub-critical at 547°F, 2235 PSIG. All shutdown bank control rods are fully withdrawn.

2. S2.OP-ST.AF-0001(Q), INSERVICE TESTING-21 AUXILIARY FEEDWATER PUMP was completed at the end of the previous shift. The procedure has just been submitP to the control room.

3. 21 AFW Pump has been left in service to provide feed while preparations are in progress for performing S2.OP-ST.AF-0002.

INITIATING CUE:

You are the Unit 2 CRS. Review the completed S2.OP-ST.AF-0001(Q), INSERVICE TESTING-21 AUXILIARY FEEDWATER PUMP.

Nuclear Common Page 5 of 5

PSEG Internal Use Only PSEG NUCLEAR L.L.C.

SALEM/OPERATIONS S2.OP-ST.AF-0001(Q) - REV. 14 INSERVICE TESTING - 21 AUXILIARY FEEDWATER PUMP USE CATEGORY: I REVISION

SUMMARY

Biennial Review Performed: Yes _No

_.[ NA - Moved vibration point 3A from Technical Specification Acceptance Criteria to Non-Technical Specification Acceptance Criteria. The ASME O&M 10 code, to which we are committed, does not require monitoring of Axial Vibrations on the line bearings of pumps in the IST program.

(80024023)

The following changes deal with the removal and replacement of the Panametric Ultra Sonic Flow Monitor with the Controlotron. All references to the Panametrics Ultra Sonic Flow montior have been deleted. These changes are editorial in nature as previously approved in S1.OP-ST.AF-0001(Q).

(80019923) 2.6 - changed procedure from Panametrics to Controlotron.

5.1.3 - added step for the Maintenance Technician to perform a zero flow adjustment for Controlotron.

5.1.17 - added step to turn Controlotron power off.

7.5.2.F - replaced Panametrics procedure with Controlotron procedure.

• , 4.0 - added recording of Controlotron Data following zero adjustment.

• , 2.0 - replaced Panametrics with Controlotron.

• , 3.0 - replaced Panametrics with Controlotron.

IMPLEMENTATION REQUIREMENTS None PSE&G Effective Date Y44

/

CONTROL COPY #

APPROVED:

Or

/LS Op'eration Manager - Salem Page 1 of 1 Date

S2OP-ST.AF-0001(Q)

INSERVICE TESTING - 21 AUXILIARY FEED PUMP TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PU RPO SE...............................................

2 2.0 PREREQUISITES.........................................

2 3.0 PRECAUTIONS AND LIMITATIONS............................

3 4.0 EQUIPMENT/MATERIAL REQUIRED 4

5.0 PROCEDURE 5

5.1 IST of 21 AF Pump and 21AF4 Check Valve...................

5 5.2 Acceptance Criteria..................................

9 5.3 Completion and Review................................

9 6.0 RECORDS 12

7.0 REFERENCES

12 ATTACHMENTS Instrument and Test Equipment Data.......................

14 21 AF Pump Surveillance Data..........................

16 Independent Verification 18 Comnletion Sign-Off Sheet...........-----------------

19

.

t Page 1 of 20 S. em 2 Rev. 14

s2.OP-ST.AF-0001(OJ 1.0 PURPOSE 1.1 Provides instructions necessary to perform Inservice Inspection and Testing LAW Technical Specification 4.0.5 for the following components:

[C0265]

21 Auxiliary Feed Pump 21AF4 Check Valve (Partial Open)

This requirement is applicable in Modes 1-3.

1.2 Perform Technical Specification Surveillance 4.7.1.2.b. 1 (Developed Head).

This requirement is applicable in Modes 1-3.

[C0265]

1.3 Performance of this procedure is required at least once per 92 days in Modes 1-3 on a STAGGERED TEST BASIS, prior to entry into Mode 3 if NOT previously performed in the last 92 days, or as otherwise specified in post-maintenance operational retest requirements.

2.0 PREREQUISITES 162.1

ýý 2.2 AZ 2.3 2.4

/-

2.5 IDENTIFY sections of this procedure NOT to be performed with "N/A".

REVIEW components "Off Normal and Off-Normal Tagged" List(s) for system and support system(s) associated with evolution to be performed in this procedure.

ENSURE the applicable SAP Order number(s) and Reason for Test are recorded on, Section 1.0.

IF this surveillance is being performed to verify post-maintenance operability of 21 Auxiliary Feedwater Pump OR to establish new baseline data, THEN NOTIFY the IST Implementation Engineer.

ATTACH a copy of S2.RA-ST.AF-0001(Q), Inservice Testing 21 Auxiliary Feedwater Pump Acceptance Criteria.

Page 2 of 20

[C05831 Salem 2 Rev. 14

O 2.6 SI2.7 ENSURE Maintenance Technician is available to perform the following

Vibration Data Collection of 21 Auxiliary Feedwater Pump utilizing a DLI Watchman DC-7 Data Collector.

SC.IC-DC.ZZ-0003(Q), Controlotron Model 960 and 990 Flow Computer Zero Adjustment.

Direct Maintenance Technician to PERFORM the following:

PROGRAM the DLI Watchman DC-7 Data Collector to record 21 Auxiliary Feedwater Pump vibration.

[C0600]

RECORD calibration data for the M&TE and Vibration Data Collection Equipment listed in Attachment 1, Section 2.0 and 3.0.

[C0289]

INSTALL Temporary Test Equipment as specified in Attachment 1, Section 3.0 3.0 PRECAUTIONS AND LIMITATIONS

/

-3.1

• 1 3.2 b;

3.3 f

3.4 S3.5 S3.6 Procedure Use and adherence policy as found in NC.NA-AP.ZZ-0001(Q),

Nuclear Procedure System, is applicable to this procedure.

Steps identified with a dollar sign ($) are those items required to meet Technical Specification acceptance criteria. Such steps, if not satisfactorily completed, may have reportability requirements and should be brought to immediate attention of the OS/CRS.

22 AND 23 AF Pumps are NOT in operation.

Do NOT operate 21 AF Pump if suction pressure is < 8.2 psig.

21 AF Pump is to be stopped should the motor winding temperature exceed 266°F.

21 AF Pump oil levels are to be maintained at 1/2 to 3/4 full.

IF in Modes 1-3 and Auxiliary Feedwater System is NOT required, THEN S2.OP-PT.AF-0002(Q), Auxiliary Feedwater Backleakage is to be performed 30 to 60 minutes following pump shutdown.

3.8 IF substitution of Measuring and Test Equipment (M&TE) is required, THEN the IST Implementation Engineer has specified range, accuracy and substitution in the Comments Section of Attachment 4.

[C0270]

documented Page 3 of 20 IST S2.OP-ST.AF-ooo1(Q)

Salem-2 Rev. 14

4&3.9 t

3.10 S2.OP-ST.AF-0001(Q)

IF the indicating needle of a test gauge used for obtaining pump performance data is operating erratically due to hydraulic (i.e., flow or pressure) fluctuations, THEN gauge indication may be dampened by throttling the instrument root valve to reduce indicated fluctuations. When this dampening technique is utilized, the operator shall alternately open and close the instrument root valve several times to verify unobstructed pressure communication while observing the instrument reading.

Pump flow is required to be established at the reference value indicated in S2.RA-ST.AF-0001(Q), Inservice Testing - 21 Auxiliary Feedwater Pump Acceptance Criteria (as close as reasonably achievable) prior to acquisition of pump performance data. The indicated allowable band (+/-2% of Reference Value) was specifically incorporated to allow for instrument fluctuations about the Reference Value, and is NOT intended to be utilized as an allowable flow adjustment band.

4.0 EQUIPMENT/MATERIAL REQUIRED 4.1 M&TE:

DLI Watchman DC-7 Data Collector DLI Triaxial Accelerometer One (1) Heise Gauge or equivalent, range 0-60 psig, accuracy +/-0.1 % of full scale and total uncertainty of +/-0.06 psig or better.

One (1) Heise Gauge or equivalent, range 0-3000 psig, accuracy +/-0.1% of full scale and total uncertainty of +/-3.0 psig or better.

4.2 Additional Tools and Equipment:

JA Master Key

4.3 Procedure(s)

Copy of S2.RA-ST.AF-0001(Q), Inservice Testing - 21 Auxiliary Feed Pump Acceptance Criteria Page 4 of 20 Salem2 Rev. 14

SZ.OP-ST.AF-0001(Q) 5.0 PROCEDURE 5.1 IST of 21 AF Pump

&/-

5.1.1 PLACE No. 2 Aux Feed Tank Heater Pump in STOP.

At 5.1.2 IF 21 AF Pump is in service, THEN:

5.1.3

_*A 5.1.4 A. ENSURE 23 and 24 Steam Generators have sufficient level to stop auxiliary feed supply for duration of this test.

B.

STOP 21 AF Pump.

Direct Maintenance Technician to:

A. PERFORM Controlotron Zero Flow Adjustment IAW SC.IC-DC.ZZ-0003(Q), Controlotron Model 960 and 990 Flow Computer Zero Adjustment.

B.

RECORD Controlotron calibration data AND completion data in Attachment 1, Section 4.0.

ENSURE the following valves are OPEN:

A. 21AF101, AF PUMP RECIRC ISOL B.

21AF40, AF PMP RECIRC V Al]1Ž4 5.1.5 IF in Modes 1-3, THEN ENTER T/S 3.7.1.2 for 21 Auxiliary Feedwater Pump.

i-i5.1.6 DECREASE the following valve demands to 0%:

23AF21, STEAM GENERATOR INLET VALVE

+

24AF21, STEAM GENERATOR INLET VALVE CAUTION When starting 21 AF Pump, the "21 START" pushbutton must be pressed for at least five (5) seconds to preclude an inadvertant S/G Blowdown and Sample isolation.

5.1.7 5.1.8 4-5.1.9 START 21 AF Pump.

ENSURE 21AF40, AF PMP RECIRC V, modulating valve is OPEN.

CLOSE 21AF40-A/S, AIR SUPPLY TO 21AF40 (2SV537),

AND VENT air supply at regulator petcock.

Page 5 of 20 Salem 2 Rev. 14

s.OP-ST.AF-OOO1(Q)

6.

5.1.10 A

t 5.1.11 4

5.1.12 AdA UNLATCH 21AF40 handwheel AND THROTTLE 21AF40 to obtain the reference value for flow identified in S2.RA-ST.AF-0001(Q), Inservice Testing - 21 Auxiliary Feedwater Pump Acceptance Criteria as indicated on the Controlotron.

When 21 Auxiliary Feed Water Pump has operated for > 2 minutes at stable conditions, PERFORM the following:

Direct Maintenance Technician to OBTAIN "Vibration Readings" on 21 Auxiliary Feedwater Pump utilizing the DLI Watchman DC-7 Data Collector.

RECORD "Pump Performance Data" on Attachment 2, Section 2.0.

Direct Maintenance Technician to PERFORM the following:

A. DOWNLOAD the DLI Watchman DC-7 Data Collector to the ALERT Computer.

B.

IF a DLI Printer is available, THEN:

AL4 2.

4P PRINT 21 Auxiliary Feedwater Pump vibration results.

ATTACH a copy of the 21 Auxiliary Feedwater Pump vibration results to this procedure.

C. IF a DLI Printer is NOT available, THEN RECORD 21 Auxiliary Feedwater Pump vibration readings from the DLI Computer on Attachment 2, Section 1.0.

D. REMOVE Temporary Test Equipment specified in Attachment 1, Section 3.0.

E. IF Electronic Pressure Modules (digital) were NOT used, THEN COMPLETE Attachment 1, Section 4.0, Post Test Calibrations.

Page 6 of 20 NOTE After pump conditions are as stable as the system permits, 21 AF Pump is required to be operated for at least 2 minutes prior to acquiring "Vibration Readings" and "Pump Performance Data".

Sale m*2 Rev. 14

<4

- 5.1.13

" f --- 5.1.14

/-

5.1.15 41-1 5.1.16

/Yf 5.1.17 6

5.1.18 5.1.19 A0 5.1.20

- 5.1.21 Salem 2 S2.OP-ST.AF-0001(Q)

POSITION 21AF40 handwheel to NEUTRAL AND LATCH handwheel.

CLOSE 21AF40 air supply regulator petcock AND OPEN 21AF40-A/S.

RECORD 21AF4 PARTIAL OPEN "Test Results" by initialing SAT or UNSAT column using Acceptance Criteria in Attachment 2, Section 3.0.

IF 21 AF Pump is NOT required to maintain Steam Generator levels, THEN:

A. STOP 21 AF Pump.

B.

RAISE demand to 98% for following valves:

23AF21, STEAM GENERATOR INLET VALVE 24AF21, STEAM GENERATOR INLET VALVE C.

IF in Modes 1-3, THEN PERFORM S2.OP-PT.AF-0002(Q), Auxiliary Feedwater Backleakage, 30 to 60 minutes following pump shutdown.

[C0270]

PLACE Controlotron Power Supply Switch to OFF position.

IF 21 AF Pump is required to maintain steam generator water level, THEN ADJUST the valve demands to the following valves, as required:

23AF21, STEAM GENERATOR INLET VALVE 24AF21, STEAM GENERATOR INLET VALVE PLACE No. 2 Aux Feed Tank Heater Pump in AUTO.

IF in Modes 1-3, THEN EVALUATE T/S 3.7.1.2 for continued applicability.

Direct a second Operator to PERFORM Independent Verification of the following:

Calculations performed in Attachment 2.

[C0284]

Valve positions in Attachment 3.

[C0290]

Page 7 of 20 Rev. 14

Jfk 5.1.22 S2.OP-ST.AF-0001(Q)

IF this surveillance is being performed as a regular scheduled surveillance OR to verify post-maintenance operability, THEN RECORD "Test Results" by initialing SAT or UNSAT column using Acceptance Criteria in Attachment 2, Sections 1.0, 2.0 and 3.0.

5.1.23 IF this surveillance is being performed to establish new baseline data, THEN IST Implementation Engineer PERFORM the following:

IST

$ IST A. EVALUATE the data AND DETERMINE if the specified components meet minimum design requirements.

B.

RECORD "Test Results" by initialing SAT or UNSAT column using the Acceptance Criteria in Attachment 2, Sections 1.0, 2.0 and 3.0.

Page 8 of 20 Salem 2 Rev. 14

s 2.OP-ST.AF-0001(Q) 5.2 pletion and Review COMPLETE Attachment 4, Sections 1.0 and 2.0, AND FORWARD this procedure to the CRS for review.

5.3 Com!

45.3.1

(,ipIDArF 5.3.2 T V 1 - 04C-atjt)ýDf J5 Co/vP, b4Tr5 CA,), r)Ai 1-CRS PERFORM the following:

4'W A.

REVIEW this procedure with Attachments 1-4 for completeness and accuracy.

B.

IF all pump Technical Specification Acceptance Criteria (ASME) parameters are SAT AND in the ACCEPTABLE RANGE, THEN:

DECLARE Pump OPERABLE.

IF pump is currently on an increased test frequency, THEN EVALUATE conditions required to return the pump to normal test frequency 1AW NC.WM-AP.ZZ-0003(Q),

Regular Maintenance Process and NC.NA-AP.ZZ-0070(Q),

Inservice Testing Program.

C.

IF ANY pump Technical Specification Acceptance Criteria (ASME) parameter is SAT AND in the ALERT RANGE, AND NO pump Technical Specification Acceptance Criteria (ASME) parameter is UNSAT OR in the REQUIRED ACTION RANGE, THEN:

DECLARE pump OPERABLE.

IF pump is currently on a normal test frequency, THEN INITIATE a change to place pump on increased test frequency IAW NC.WM-AP.ZZ-0003(Q), Regular Maintenance Process and NC.NA-AP.ZZ-0070(Q), Inservice Testing Program.

(step continued on next page)

Salem 2 Page 9 of 20 Rev. 14 Acceptance Criteria 5.2.1 This surveillance is satisfactory when Attachment 2 is completed with equipment listed meeting the Technical Specification Acceptance Criteria (ASME) stated in the attachment.

OR 5.2.2 This surveillance is unsatisfactory.

A4 A. INITIATE NOTF(s) to correct unsatisfactory condition(s).

AM--

B.

RECORD NOTF number(s), and reason for unsatisfactory completion on Attachment 4 in the Comments Section.

WA*J I

S2OP-ST.AF-0001(Q) 5.3.2 (continued)

,4Al, b

T CA'p r VAT16 INITIATE a NOTF LAW NC.WM-AP.ZZ-OO0O(Q),

Notification Process.

RECORD NOTF number(s) on Attachment 4 in the Comments Section.

NOTIFY the Vibration Program Manager to promptly evaluate the test data.

NOTIFY the IST Implementation Engineer.

(step continued on next page)

Page 10 of 20 D. IF ANY pump Technical Specification Acceptance Criteria (ASME) parameter is UNSAT, in the REQUIRED ACTION RANGE, THEN:

DECLARE pump inoperable.

EVALUATE Technical Specifications for system operability.

INITIATE a NOTF LAW NC.WM-AP.ZZ-OOOO(Q),

Notification Process.

RECORD NOTF number(s) on Attachment 4 in the Comments Section.

E.

IF ANY pump Non-Technical Specification Acceptance Criteria (Non-ASME) parameter is SAT AND in the ALERT RANGE, THEN:

INITIATE a NOTF IAW NC.WM-AP.ZZ-OOOO(Q),

Notification Process.

RECORD NOTW number(s) on Attachment 4 in the Comments Section.

NOTIFY the Vibration Program Manager.

NOTIFY the IST Implementation Engineer.

F.

IF ANY pump Non-Technical Specification Acceptance Criteria (Non-ASME) parameter is UNSAT, in REQUIRED ACTION RANGE, THEN:

Salem 2 Rev. 14

S2.OP-ST.AF-0001(Q) 5.3.2 (continued)

(,djtPL..

TW G. IF Technical Specification Acceptance Criteria (ASME) for ANY Check Valve is UNSAT, THEN:

I 9W.D-,At T

jtrrTAt-0 5.3.3 5.3.4 END OF PROCEDURE SECTION Page 11 of 20 DECLARE the Check Valve inoperable.

EVALUATE Technical Specifications for system operability.

INITIATE a NOTF IAW NC.WM-AP.ZZ-0000(Q),

Notification Process.

RECORD NOTF number(s) on Attachment 4 in the Comments Section.

H. COMPLETE Attachment 4, Section 3.0.

I.

FORWARD this procedure to the STA for review.

STA PERFORM the following:

A. REVIEW this procedure with Attachments 1-4 for completeness and accuracy.

B.

COMPLETE Attachment 4, Section 3.0.

C. FORWARD this procedure to the OS/CRS for review and approval.

OS/CRS PERFORM the following:

A. REVIEW this procedure with Attachments 1-4 for completeness and accuracy.

B.

COMPLETE Attachment 4, Section 3.0.

C.

PLACE this procedure in the IST IMPLEMENTATION ENGINEER REVIEW REQUIRED mail slot.

Salem 2 Rev. 14

S2.OP-ST.AF-0001(Q) 6.0 RECORDS 6.1 Retain the following IAW NC.NA-AP.ZZ-0011(Q), Records Management Program:

• -4 Copy of S2.RA-ST.AF-0001(Q), Inservice Testing - 21 Auxiliary Feed Pump Acceptance Criteria, if applicable Pump DLI Vibration Analyzer Printout

7.0 REFERENCES

7.1 Updated Final Safety Analysis Report:

7.1.1 3.9.4, Inservice Testing of Pumps and Valves 7.1.2 10.4.7.2, Auxiliary Feedwater System 7.1.3 15.2.8, Loss of Normal Feedwater

7.2 Drawings

7.2.1 205336, No. 2 Unit Auxiliary Feedwater

7.3 Procedures

7.3.1 NC.WM-AP.ZZ-0000(Q), Notification Process 7.3.2 NC.WM-AP.ZZ-0001(Q), Work Management Process 7.3.3 NC.WM-AP.ZZ-0002(Q), Performance Improvement Process 7.3.4 NC.NA-AP.ZZ-0022(Q), Measuring & Test Equipment, Lifting & Rigging and Tool Control 7.3.5 NC.NA-AP.ZZ-0050(Q), Station Testing Program 7.3.6 SH.RA-AP.ZZ-0105(Q), IST Program Management

7.4 Others

7.4.1 OM-6, Inservice Testing of Pumps in Light-Water Reactor Power Plants (1988 Edition) 7.4.2 OM-10, Inservice Testing of Valves in Light-Water Reactor Power Plants (1988 Edition) 7.4.3 Salem Generating Station IST Manual 7.4.4 NUREG-1482, Guidelines for Inservice Testing at Nuclear Power Plants Page 12 of 20 Salem 2 Rev. 14

S2.OP-ST.AF-0001(Q) 7.5 Cross-

References:

7.5.1 Technical Specifications - Unit 2:

A. 4.0.5, Inservice Inspection and Testing B.

4.7.1.2.b. 1, Auxiliary Feedwater System

7.5.2 Procedures

A. NC.NA-AP.ZZ-0011(Q), Records Management Program B.

NC.WM-AP.ZZ-0003(Q), Regular Maintenance Process C.

NC.NA-AP.ZZ-0070(Q), Inservice Testing Program D. S2.OP-PT.AF-0002(Q), Auxiliary Feedwater Backleakage E.

SC.OP-AP.ZZ-0106(Q), Operability Determination F.

S2.RA-ST.AF-0001(Q), Inservice Testing - 21 Auxiliary Feed Pump Acceptance Criteria G. SC.IC-DC.ZZ-0003(Q), Controlotron Model 960 and 990 Flow Computer Zero Adjustment.

7.6 Commitments

7.6.1 C0265 - NSO LER 311/89-015-00 7.6.2 C0270 - NRC GL 88-03 7.6.3 C0275 - NRC INSP 90-03 7.6.4 C0283 - NRC VIOL 311/87-18-0 7.6.5 C0284 - NRC VIOL 272/90-014-00 7.6.6 C0289 - INSTRUMENT CALIBRATION REQUIREMENTS 7.6.7 C0290 - NRC INFO 84-51 7.6.8 C0583 - NRC VIOL 50-272/94-21 7.6.9 C0600 - NLR-N89196, Salem IST Conduct Page 13 of 20 Salem 2 Rev. 14

S2.OP-ST.AF-0001(Q)

ATTACHMENT 1 (Page 1 of 2)

INSTRUMENT AND TEST EQUIPMENT DATA 1.0 SAP ORDER DATA SAP Order Number(s):

__Reason for Test S__

_/Scheduled Surveillance Post-Maintenance Operability Establish New Baseline Data Other (Explain in Comments) 2.0 VIBRATION DATA COLLECTION EQUIPMENT:

Instrument/Test Descrition Calibration Initials Equipment DcpoDue Date DLI Watchman DC-7 Data Collector DLI Triaxial Accelerometer

/--

0

_,3 _______

3.0 TEMPORARY TEST EQUIPMENT Temporary

)Installation Point Installation Removal Test Equipment Cal. Due Date Initials Date Initials Date Heise CM or

/,]

Instr. Vent for equivalent 2PL8647 0-60 psig Date: %-/,a,3 (suction pressure)

(1)(2)

HequivalenCM or 7

Instr. Vent for 00 pig 2PL1678 (12 0-3000 psig Date: 7"-#'

(discharge pressure)

(1)(2)

(1)

Installation of suction and discharge pressure gauges at same elevation ensures consistent pump performance data.

(2)

Maintenance Techincian shall ensure the pressure gauge sensing line is filled and vented during installation.

Salem 2 Page 14 of 20 Rev. 14

S2.OP-ST.AF-0O01(Q)

ATTACHMENT 1 (Page 2 of 2)

INSTRUMENT AND TEST EQUIPMENT DATA 4.0 CONTROLOTRON DATA Description ID Number Calibration Overdue Date Controlotron 2FL14752 4"

SC.IC-DC.ZZ-0003(Q), Controlotron Model 960 and 990 Flow Computer Zero Adjustment has been completed.

Performed By:

.4,v *2-v?6--

Date: //-,0-dP Time:

96,0 5.0 POST TEST CALIBRATION RESULTS Instrument/Test II) Number SAT UNSAT Initials Equipment Heise CM or equivalent

//4 0-60 psig (1)

Heise CM or equivalent 0-3000 psig (1)

(1) Post-Test Calibration is NOT required when Electronic Pressure Modules (digital) are used.

Performed by 6 A.

Date Performed by /

6i A

M&TE Supervisor Date

//-/-

6_a Page 15 of 20 M&TFarctnician n

- e57 a, Sal em 2 Rev. 14

S2.OP-ST.AF-0001(Q)

ATTACHMENT 2 (Page 1 of 2) 21 AUXILIARY FEEDWATER PUMP SURVEILLANCE DATA 1.0 VIBRATION READINGS:

Vibration Position 1:

MOTOR OUTBOARD Vibration Position 2:

MOTOR INBOARD Vibration Position 3:

PUMP INBOARD Vibration Position 4:

PUMP OUTBOARD Test Results 21 AF Pump Vibration Results Acceptable Range Alert Range Required Action SAT SAT UNSAT Non-Technical Specification Acceptance Criteria (Non-ASME)

Vibration Position 1A m c in/sec (1)

Vibration Position 1H j),_

__in/se_

(I)__

Vibration Position 1V 6, 01-7 inse (1)

Aý Vibration Position 2A o.1,,o in/sec (1)

Vibration Position 2H in/see (1)

Vibration Position 2V

,6o in/sec (1)

Vibration Position 3A 0,

-7 in/see (1)

Technical Specification Acceptance Criteria (ASME)

$ Vibration Position 3H in/sec (1)

$ Vibration Position 3V in/se (1)

$ Vibration Position 4A in/sec (1)

$ Vibration Position 4H in/sec (1)

$ Vibration Position 4V c',.0,_

in/sec (1)

Acceptance Criteria:

Vibration Results for the 21 Auxiliary Feedwater Pump are within bands specified in S2.RA-ST.AF-0001(Q), Inservice Testing 21 Auxiliary Feedwater Pump Acceptance Criteria OR data represents new baseline data as determined by the IST Implementation Engineer.

(1)

Vibration data is only required to be recorded, when a DLI Vibration Analyzer Printout is NOT available.

Page 16 of 20 Salem 2 Rev. 14

s2.OP-ST.AF-0001(Q)

ATTACHMENT 2 (Page 2 of 2) 21 AF PUMP SURVEILLANCE DATA 2.0 PUMP PERFORMANCE DATA:

Pump Performance Parameter Parameter Value Test Results Acceptable Range SAT Alert Range SAT Required Action UNSAT Pump Suction Pressure RUNNING psig (Heise Gauge)

(A) c 3 Pump Discharge Pressure (Heise Gauge)

(B) / psi

Differential Pressure (B) - (A) = psid psi 2 psid Pump Recirc. Flow Rate gpm (2FL14752)

/I/

I I

Technical Specification Acceptance Criteria (ASME):

Measured values are within bands specified in S2.RA-ST.AF-0001(Q), Inservice Testing 21 Auxiliary Feedwater Pump Acceptance Criteria OR data represents new baseline data as determined by the IST Implementation Engineer.

Independent Verification of Calculation Performed By: j7j *

[C0284]

3.0 CHECK VALVE DATA:

Check Stroke Technical Specification Test Results Valve Acceptance Criteria (ASME)

SAT UNSAT Flow is > the minimum value identified in the P

Acceptable Range of S2.RA-ST.AF-0001(Q),

21AF4 OPARN Inservice Testing - 21 Auxiliary Feedwater Pump S OPEN Acceptance Criteria, as indicated on the Controlotron.

Page 17 of 20 Salem 2 Rev. 14

S2.OP-ST.AF-W001(Q)

ATTACHMENT 3 (Page 1 of 1)

INDEPENDENT VERIFICATION Component Description Normal Position IV 21AF40 AF PMP RECIRC V Handwheel LATCHED in NEUTRAL position 21AF40-A/S AIR SUPPLY TO 21AF40 (2SV537) 0 21AF40 Regulator downstream of 21AF40-A/S Regulator Petcock supplying 2SV537 23AF21 STEAM GENERATOR INLET VALVE Demand 98%

(1) 24AF21 STEAM GENERATOR INLET VALVE Demand 98%

(1)

(1)

Valve may be throttled as required for S/G level control when AFW System is in service.

Page 18 of 20 Salem 2 Rev. 14

ATTACHMENT 4 (Page 1 of 2)

COMPLETION SIGN-OFF SHEET

1.0 COMMENTS

(Include test deficiencies and corrective actions.)

S2.OP-ST.AF-0001(Q)

Page 19 of 20 S~e~m2 Rev. 14

S2.OP-ST.AF-OO1(O)

ATTACHMENT 4 (Page 2 of 2)

COMPLETION SIGN-OFF SHEET

2.0 SIGNATURES

Print 62

/14' ~Q14; Initials

• <4 INDEPENDENT VERIFICATION:

2!-DA ~4XA t.4~

42 S....

S....

/'::

.K.

Date

//-/ -O5*

H./-

f,

...7 1/- I -o--.

3.0 STA REVIEW AND OS/CRS FINAL REVIEW AND APPROVAL:

This procedure with Attachments 1-4 is reviewed for completeness and accuracy.

All deficiencies, including corrective actions, are clearly recorded in the COMMENTS Section of this attachment. Technical Specification compliance, procedure compliance, and Acceptance Criteria are evaluated.

[C0283]

CRS STA OS/CRS Date:

Date:

Date:

4.0 IST IMPLEMENTATION ENGINEER REVIEW:

Test Results are reviewed for acceptability. If required, revision of Acceptance Criteria and test frequency change is initiated. Forward completed procedure to Operations Staff.

IST Implementation Engineer Date:

Page 20 of 20 Signature:

Signature:

Signature:

Signature:

Sal;e~m 2 Rev. 14

USE CATEGORY: II REVISION

SUMMARY

Biennial Review performed:

Yes V No The following OTSC's were evaluated for incorporation into this Revision: None 80024023, changed designation of Vibration point 3A to Non Technical Specification acceptance criteria, and added change to Reference Section.

Revision bars have been utilized to indicate changes.

IMPLEMENTATION REQUIREMENTS

+

Effective Dat te6 APPROVED:

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20021027 PSEG Internal Use Only IST GROUP S2.RA-ST.AF-0ool(Q) - REV. 5 INSERVICE TESTING 21 AUXILIARY FEED PUMP ACCEPTANCE CRITERIA Page 1 of 1

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20021027 INSERVICE TESTING 21 AUXILIARY FEED PUMP ACCEPTANCE CRITERIA TABLE OF CONTENTS SECTION TITLE 1.0 PURPOSE...................

2.0 PREREQUISITES..............

3.0 PRECAUTIONS AND LIMITATIONS 4.0 EQUIPMENT/MATERIAL REQUIRED 5.0 PROCEDURE................

6.0 RECORDS..................

7.0 REFERENCES

ATTACHMENTS 21 AF Pump Surveillance Data Salem 2 PAGE S.

2 2

S.

2

.* 2 3

Acceptance Criteria...............

5 Page 1 of 6 Rev. 5 s2. -ST.AF-ooo, Q)

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20021027 S2.RA ST.AF-oooI(Q) 1.0 PURPOSE To provide the acceptance criteria necessary to evaluate the Inservice Testing data IAW Technical Specifications 4.0.5 and 4.7.1.2.b. 1 relative to performance of S2.OP-ST.AF-0001(Q), Inservice Testing - 21 Auxiliary Feed Pump. [C0265]

2.0 PREREOUISITES None 3.0 PRECAUTIONS AND LIMITATIONS None 4.0 EQUIPMENT/MATI-ERIAL REQUIRED None 5.0 PROCEDURE None END OF PROCEDURE SECTION Salem 2 Page 2 of 6 Rev. 5

ALL ACTIVE ON-THE-SPOFTCHANGES MUST BE ATTACHED FOR FIELD USE 20021027 s2.RA.ST.AF..000(Q) 6.0 RECORDS None

7.0 REFERENCES

7.1 UIpdated Final Safety Analysis Report:

7.1.1 Section 3.9.4, Inservice Testing of Pumps and Valves 7.1.2 Section 10.4.7.2, Auxiliary Feedwater System 7.1.3 Section 15.2.8, Loss of Normal Feedwater 7.2 Technical Specifications - Unit 2:

7.2.1 3.7.1.2, Auxiliary Feedwater System

7.3 Drawings

7.3.1 205336, No. 2 Unit Auxiliary Feedwater

7.4 Procedures

7.4.1 NC.NA-AP.ZZ-0050(Q), Station Testing Program 7.4.2 NC.NA-AP.ZZ-0070(Q), Inservice Testing Program 7.4.3 NC.WM-AP.ZZ-0000(Q), Notification Process 7.4.4 NC.WM-AP.ZZ-0001(Q), Work Management Process 7.4.5 NC.WM-AP. ZZ-0002(Q), Performance Improvement Process 7.4.6 NC.WM-AP.ZZ-0003(Q), Regular Maintenance Process Salem 2 Page 3 of 6 Rev. 5

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20L21027 7.5 s2.RA-ST.AF-0ooo (Q)

Others:

7.5.1 NUREG-1482, Guidelines for Inservice Testing at Nuclear Power Plants 7.5.2 Salem Generating Station IST Manual 7.5.3 ASME Section XI Subsection IWP (1989 Edition) 7.5.4 ASME Standard OMa-1988, Part 6 7.5.5 NOTF #20001328, Potential Non-Conservative Technical Specification (AFW) 7.5.6 NFS99-288, Salem Units 1 & 2 Degraded Flow Head Curves for AFW Pumps 7.5.7 Design Calculation F-C-AF-MDC-0445, Auxiliary Feedwater Hydraulic Analysis 7.5.8 80024023, Changed to IST Acceptance Criteria 7.6 Cross-

References:

7.6.1 Technical Specifications - Unit 2:

A. 4.0.5, Inservice Inspection and Testing B.

4.7.1.2.b.1, Auxiliary Feedwater System

7.6.2 Procedures

A.

S2.OP-ST.AF-O001(Q), Inservice Testing - 21 Auxiliary Feed Pump B.

SH.RA-AP.ZZ-0105(Q), IST Program Management

7.7 Commitments

7.7.1 C0265 - NSO/LER/89-015-00 Salem 2 0o.

A gr

• 9 UJL 0 Rev. 5 I

ALL ACTIVE ON-THE-SPOT

-CHANGES MUST BE ATTACHED FOR FIELD USE 20021027 s2.RA-ST.AF-ooo(Q)

ATTACHMENT 1 21 AF PUMP SURVEILLANCE DATA ACCEPTANCE CRITERIA (Page 1 of 2) 1.0 PUMP VIBRATION READINGS:

21 AF Pump Reference Acceptance Alert Required Vib. Pos.

Value Date Range Range Action Range (insee)

SAT SAT UNSAT lA (2) 0.14 0.0 - 0.280

> 0.280 - 0.700

> 0.700 1H (2) 0.17 0.0 - 0.306

> 0.306 - 0.700

> 0.700 1V (2) 0.05 0.0 - 0.125

> 0.125 - 0.300

> 0.300 2A (2) 0.11 0.0 - 0.275

> 0.275 - 0.660

> 0.660 21 (2) 0.18 0.0 - 0.324

> 0.324 - 0.700

> 0.700 2V (2) 11/14/1999 0.0 - 0.225

> 0.225 - 0.540 0.540 3A (2) 0.44 (1) 0.0 - 0.2

.640 - 0.765

> 0.765 31 (3) 0.53 0.0 - 0.730

> 0.730 - 0.855

> 0.855 3V (3) 0.40 0.0 - 0.600

> 0.600 - 0.700

> 0.700 4A (3) 0.42 0.0 - 0.620

> 0.620 - 0.745

> 0.745 4H (3) 0.63 0.0 - 0.830

> 0.830 - 0.955

> 0.955 4V (3) 0.35 0.0-- 0.525

> 0.525 - 0.700

> 0.700 (1)

Reference values collected under Order # 50007044 (2)

Non-Technical Specification (Non-ASME) Acceptance Criteria.

(3)

Technical Specification (ASME) Acceptance Criteria.

Salem 2 Page 5 of 6 D

-VT. a

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20021027 s2.RA-ST.AF-O0ol(Q)

ATTACHMENT 1 21 AF PUMP SURVEILLANCE DATA ACCEPTANCE CRITERIA (Page 2 of 2) 2.0 PUMP HYDRAULIC DATA:

Test Results Pump Acceptable Alert Required Performance Value Date Range Range Action Parameter SAT SAT UNSAT Low High Low High Suction Pressure Pump Running (A) 24 psi

.;W Pump Discharge 1420.0 psig a: 1305.0

13,5-0.,-

Pressure (B) 05/05/93

__(5)

S.....(5)

'" :"" T Differential Pressure (4) 1359 13-9 1396.0 psid 1<05.7

>"1536 (B"-(A) = psid 153 15

.6 9

Pmp Recirc Flow Rate 16.0 gpm 157-163

< 157

> 163 Flow-Rate

-(6)

(6)

(4)

Reference values collected under WO #930406034.

(5)

The 1305.0 psig minimum discharge pressure is the Technical Specification 4.7.1.2.b. I minimum pump discharge pressure while in recirculation flow of Ž 1275 psig plus 30 psig for instrument uncertainty (PR #970821298).

(6)

Values outside of those listed in the acceptance range do not necessarily make the pump inoperable, but do invalidate performance of the procedure.

(7)

Minimum pump differential pressure at 160 gpm is Ž 1369 psid IAW F-C-AF-MDC-0445, Rev 2, Auxiliary Feedwater Hydraulic Analysis.

Salem 2 Page 6 of 6 Rev. 5

STATION:

SYSTEM:

TASK:

TASK NUMBER:

JPM NUMBER:

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MrvEASURE SALEM ADMINISTRATIVE (Waste Gas)

Review a radioactive gaseous waste release form 0710050302 GOLF NRC - SRO A3 ALTERNATE PATH:

L K/A NUMBER:

IMPORTANCE FACTOR:

APPLICABILITY:

EO Q

RO-]

STA

• SRO W EVALUATION SETTING/METHOD:

Room with references

REFERENCES:

Si.OP-SO.WG-0009, Rev. 25 TOOLS AND EQUIPMENT:

None VALIDATED JPM COMPLETION TIME:

13 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS:

APPROVAL:

AIjl4~

2.3.6 3.1 RO SRO N/A BARGAINING UNIT REPRESENTATIVE TRAINING SUPERVISOR or designee OýEKTIONS MýNAGER or designee CAUTION:

No plant equipment shall be operated during the performance of a JPM without the following:

1. Permission from the OS or Unit CRS;

2. Direct oversight by a qualified individual (determined by the individuw granting permission based on plant conditions).

3. Verification of the "as left" condition by a qualified individual.

ACTUAL JPM COMPLETION TIME:

Minutes ACTUAL TIME CRITICAL COMPLETION:

N/A Minutes JPM PERFORMED BY:

GRADE: D SAT D

UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE:

DATE:

Rev. 0 Page 1 of 5 Nuclear Common

SYSTEM:

TASK:

ADMINISTRATIVE (Waste Gas)

Review a radioactive gaseous waste release form TASK NUMBER:

0710050302 INITIAL CONDITIONS:

1. Unit 1 is at 100% power

2. A release from 12 Gas Decay Tank is planned for this shift. The previous shift initiated t[

paperwork.

3. The release will continue until 12 Gas Decay Tank is completely depressurized in order t allow replacement of the relief valve

4. RMS Channel 1R41D is inoperable SIMULATOR SETUP: N/A INITIATING CUE:

You are the Unit 1 CRS. S1.OP-SO.WG-0009, Attachment 2 - 12 GDT RADIOACTIVE GASEOUS RELEASE FORM, has been submitted for your approval.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated tim if satisfactory progress is being made.

Nuclear Common OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

Page 2 of 5 Rev. 0

NC.TQ-WB.ZZ-031 0(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM:

ADMINISTRATIVE (Waste Gas)

TASK:

Review a radioactive gaseous waste release form STEP STEP COMMENTS NO.

(*Denotes a Critical Step)

STANDARD EVAL (Required for UNSAT

(#Denotes a Sequential Step)

S/U evaluation) 1 Provide a copy of Si.OP-SO.WG-0009, CUE: Review Attachment 2 only. Assume completed up to the that the other sections of S1.OP-SO.WG OS/CRS signature line 0009 have been completed properly.

START TIME: review:

2 Ensure Section 1.0 (SAMPLE Verifies all lines initialed, blanks filled in REQUEST) completed correctly and signature by OS/CRS 3

Ensure Section 2.0 (SAMPLE POINT) is Both lines initialed/signed completed correctly 4

Ensure Section 3.0 (DOSE, VOLUME Determines that Estimated Final Pressure ESTIMATES AND APPROVAL-should be 0 PSIG not 10 PSIG*

Chemistry) is completed correctly If necessary CUE: Completely review the document before returning it to Chemistry Determines that line reading "IF RMS Channel 2R41 A, B, or D is inoperable - -"

should NOT be N/A*

Nuclear Common Paqe 3 of 5 Rev. 0

NC.TQ-WB.ZZ-0310(Z)

INITIAL CONDITIONS:

1. Unit 1 is at 100% power

2. A release from 12 Gas Decay Tank is planned for this shift. The previous shift initiate the paperwork.

3. The release will continue until 12 Gas Decay Tank is completely depressurized in ord to allow replacement of the relief valve

4. RMS Channel 1R41D is inoperable INITIATING CUE:

You are the Unit 1 CRS. Si.OP-SO.WG-0009, Attachment 2 - 12 GDT RADIOACTIVE GASEOUS RELEASE FORM, has been submitted for your approval.

Nuclear Common Page 5 of 5

iSEG Internal Use Only PSEG NUCLEAR L.L.C.

SALEM/OPERATIONS S1.OP-SO.WG-0009(Q) - REV. 25 DISCHARGE OF 12 GAS DECAY TANK TO PLANT VENT PSE&G USE CATEGORY: I REVISION

SUMMARY

CONTROL COPY C27 Biennial Review Performed: Yes V_ No M

The following changes to this procedure are incorporated IAW Technical Specification Amendment 234.

(800186'.'

Step 1.2 - changed "4.3.3.9, Table 4.3-13, Item la", to "6.8.4.g.1.

Steps 2.3, 2.4, 2.5, 2.6, 3.9, 3.10, 5.2.2, 5.2.2.A.1, 5.2.2.A.2, 5.2.3.A, 5.2.4, 5.2.

5.2.6, Attachment 2, Attachment 3, and Attachment 4 - changed references from Technical Specification 3.3.3.9, Radioactive Gas Effluent Monitoring Instrumentation.

to the Offsite Dose Calculation Manual.

Steps 3.7 and 5.2.4 - changed references from Technical Specification 3.11.2, Gasec" Effluents, to the Offsite Dose Calculation Manual.

0 Added Step 3.8 - to provide program requirement guidance for the changes implemented by Technical Specification Amendment 234.

0 Added Technical Specification Amendment 234 to references.

Added Technical Specification 6.8.4.g, Radioactive Effluent Controls Program, to references.

Added GL 89-01, Implementation of Programmatic Controls for Radiological Effluen Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program, to references.

IMPLEMENTATION REQUIREMENTS Technical Specification Amendment 234 Effective Date APPROVED:

Date Page 1 oi

,Z*L.b cffations Manager - Salem

PSEG Internal Use Only PSEG NUCLEAR L.L.C.

SALEM/OPERATIONS S1.OP-SO.WG-0009(Q) - REV. 25 DISCHARGE OF 12 GAS DECAY TANK TO PLANT VENT USE CATEGORY : I REVISION

SUMMARY

Added Offsite Dose Calculation Manual, to references.

0 Deleted Technical Specification 3.3.3.9, Radioactive Gas Effluent Monitoring Instrumentation, from references.

Deleted Technical Specification 3.11.2.1, 3.11.2.2, 3.11.2.3, and 3.11.2.4, Gaseous Effluents.

The following editorial changes delete redundant Chemistry, Radiation Department, and O/S signature and recording data steps. Previously approved in S1.OP-SO.WL-O001(Q). (RR1409)

Old step 5.2.8 and Attachment 2, Section 4.4 - deleted Radiation Protection Supervisor approval.

Old step 5.2.10 and Attachment 2, Section 4.7 - deleted O/S final approval.

0 Step 5.3.1 - added step to complete and attach additional chemistry paprerwork.

• , Section 3.0 - deleted the step to forward procedure to Technical Supervisor - Chemistry for completion.

• , Sections 2.0 and 3.0 - revised to align with SC.CH-TI.ZZ-0146(Q).

• , Old Section 3.0 - deleted Dose Estimates table. Data redundant to Radioactive Gaseous Release Initiation Form.

0, Step 6.0 - deleted Chemistry signoff.

Page 2 of 3

PSEG Internal Use Only PSEG NUCLEAR L.L.C.

SALEM/OPERATIONS S1.OP-SO.WG-0009(Q) - REV. 25 DISCHARGE OF 12 GAS DECAY TANK TO PLANT VENT USE CATEGORY: I REVISION

SUMMARY

+

The following changes to this procedure contain only editorial enhancements as described in NC.DM-AP.ZZ-0001(Q):

0 Upgraded to the latest administrative standards.

Changed "NCO" to "RO/PO."

0 Deleted WG MECH 001 - Gaseous Waste Disposal System Mechanical System Alignment, from references.

0 Step 3.9 - Changed NC.NA-AP.ZZ-0006(Q) to NC.WM-AP.ZZ-0002(Q), Performance Improvement Process.

Added NC.WM-AP.ZZ-0002(Q), Performance Improvement Process, in references.

0 Changed NC.NA-AP.ZZ-0003(Q), Document Management Program, to NC.NA-AP.ZZ-001 1(Q), Records Management Program.

+

Note prior to Step 5.2.11.H - revised because pressure fluctuates between "0" psig and "10" psig to during the opening of WG41.

(RR1372)

+

Steps 5.1.1.B, 5.1.1.C, 5.2.7, and Attachment 1, Section 1.0 - added Pre-Release Verification to ensure correct valve lineup if the release paperwork is delayed.

(1122342)

+

Step 5.1.3 - added to provide a termination path if the release is not to be completed.

(80019587)

Page 3 of 3

Sl.OP-SO.WG-0009(Q)

DISCHARGE OF 12 GAS DECAY TANK TO PLANT VENT TABLE OF CONTENTS SECTION TITLE 1.0 PURPOSE.....................

2.0 PREREQUISITES 3.0 PRECAUTIONS AND LIMITATIONS 4.0 EQUIPMENT/MATERIAL REQUIRED 5.0 PROCEDURE 5.1 12 Gas Decay Tank (GDT) Release 5.2 12 Gas Decay Tank Release....

5.3 Completion and Review.......

6.0 RECORDS

7.0 REFERENCES

ATTACHMENTS 12 Gas Decay Tank Alignment!Vei 12 GDT Radioactive Gaseous Relea 12 GDT Release Rate Calculation Plant Vent Flow Rate Discharge Est Completion/Sign-Off Sheet.....

fication se Form timation.

Rev. 25 Page 1 of 25 PAGE 102 112

• 13 21

2.

1

.. 11 14 16 22 23 24 Preparation Salem1

S1.oP -SO.WG-O009(Q) 1.0 PURPOSE 1.1 To provide instructions necessary to:

1.1.1 Place 12 Gas Decay Tank (GDT) in Holdup.

1.1.2 Conduct a controlled Radioactive Gas Release from 12 GDT.

[C0160]

1.2 This procedure satisfies Technical Specification 6.8.4.g. 1 for Channel Operable and Source Check prior to each release.

2.0 PREREQUISITES S2.1 REVIEW Components "Off Normal and Off-Normal Tagged" List(s) for system and support system(s) associated with the evolution to be performed in this procedure.

kt__22.2 The following systems are in service:

2.2.1 Auxiliary Building Ventilation JAW S1.OP-SO.ABV-0001(Q),

Auxiliary Building Ventilation Operation 2.2.2 Fuel Handling Building Ventilation System lAW S1.OP-SO.FHV-0001(Q),

Fuel Handling Building Ventilation Operation.

2.3 ENSURE Noble Gas Activity Monitor (1R41A & D OR 1R16) are OPERABLE (IAW the ODCM).

f 2.4 ENSURE Plant Vent Flow Rate Monitor and Sample Flow Rate Monitor are OPERABLE (LAW the ODCM).

rid 2.5 ENSURE Noble Gas Activity Monitor lR41A & D is OPERABLE (IAW the ODCM).

S 2.6 ENSURE Iodine Sampler and Particulate Sampler (Chemistry Dept.) are OPERABLE (IAW the ODCM).

3.0 PRECAUTIONS AND LIMITATIONS 3.1 Procedure Use and adherence policy as found in NC.NA-AP.ZZ-0001(Q),

Nuclear Procedure System, is applicable to this procedure.

S3.2 DO NOT release more than one GDT at a time.

3.3 DO NOT Purge Unit 1 Containment during the GDT Release.

/*

3.4 DO NOT Purge/Release Unit 1 VCT during the GDT Release.

Page 2 of 25 Salem I Rev. 25

Si.OP-SO.WG-O009(OJ 4*3.5 S3.6

/

3.7 f*"

3.8 S3.9

'4 3.10 DO NOT transfer Waste Gas from one GDT to another during the GDT release.

The actual maximum GDT release rate is 32 SCFM based on system design. The calculated maximum allowable release rate shall be > 32 SCFM. Tanks with a calculated maximum allowable release rate of < 32 SCFM shall not be released.

GDT Release shall be terminated if pressure downstream of 1WG38, Gas Decay Tank Vent Pressure Control Valve, is > 8.0 psig. This will ensure the actual release rate does not exceed 32 SCFM (IAW the ODCM).

The program requirements of Radiological Effluent Technical Specifications (RETS) are located in the Offsite Dose Calculation Manual (ODCM) and Process Control Program (PCP).

(80018643)

Inoperability of the Noble Gas Activity Monitor (1R16, 1R12A, 1R41A & D), Iodine Sampler, Particulate Sampler, Flow Rate Monitor, or Sampler Flow Rate Monitor for

> 30 days is reportable IAW NC.WM-AP.ZZ-0002(Q), Performance Improvement Process (IAW the ODCM).

The Independent Verification requirements contained in the ODCM SHALL BE PERFORMED prior to the release of radioactive waste gas to the environment.

(970630118) 4.0 EQUIPMENT/MATERIAL REQUIRED None Page 3 of 25 Rev. 25 Salem I

Sl.OP-SO.WG-009(Q) 5.0 PROCEDURE 5.1 12 Gas Decay Tank (GDT) Release Preparation 5.1.1 ALIGN 12 GDT for Holdup as follows:

/**

A. OBTAIN a CRS Tagging Request for 12WG31, GDT INLET VALVE, in the CLOSED position and with specific instructions that this tag should only be released LAW this procedure.

SB.

PERFORM 12 GDT Holdup Alignment LAW Attachment 1, Section 1.0.

SC.

DIRECT second operator to complete Independent Verification (IV) of 12 GDT Holdup Alignment LAW Attachment 1, Section 1.0.

'5.1.2 INITIATE 12 GDT Radioactive Gaseous Release Form as follows:

/*

A. COMPLETE Attachment 2, Section 1.0.

IB.

FORWARD entire procedure to Chemistry Department for completion of Attachment 2, Sections 2.0 and 3.0.

A4A0

.3 IF Chemistry has NOT granted permission for the release, OR the release is no longer required, THEN:

A.

OBTAIN a CRS Tagging Release for 12WG31, GDT INLET VALVE.

B.

TERMINATE this procedure.

Page 4 of 25 SalemI Rev. 25

Si.OP-SO.WG-0009(Q) 5.2 12 Gas Decay Tank Release 5.2.1 ENSURE Attachment 2, Sections 2.0 and 3.0, are complete with approval for Radioactive Gaseous Release.

5.2.2 IF at least one of the following Radiation Monitors is OPERABLE, THEN ENSURE the following IAW the ODCM:

A.

IF IR41A & D, Plant Vent Noble Gas monitor is OPERABLE, THEN:

1.

ENSURE in calibration, set to alarm, and will close LWG41, Gas Decay Tank Vent Control Valve (IAW the ODCM).

2.

ENSURE 1R41 sample system flow control is OPERABLE (IAW the ODCM).

[C0332, C0333]

3.

PERFORM a source check and channel check (visual inspection of monitor read out).

4.

ENSURE 1ND17572 - 1WG41 Waste Gas Decay Tank in NORMAL.

OR B.

IF 1R16, Plant Vent In Line Noble Gas Monitor, is OPERABLE, THEN PERFORM 1R16 source check and channel check (visual inspection of monitor read out).

5.2.3 IF RMS Channel 1R41A or D is inoperable, THEN:

A.

ENSURE Chemistry Department has documented completion of the following contingency actions on Attachment 2, Section 3.4 (IAW the ODCM):

1.

ANALYZE at least two independent samples of 12 GDT contents.

2.

INDEPENDENTLY VERIFY release rate calculations by at least two technically qualified members of the Facility Staff.

3.

IF RMS Channel 1R16 is inoperable, THEN OBTAIN grab samples at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, AND ANALYZE for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

B.

PLACE 1ND17572 - IWG41 Waste Gas Decay Tank in BLOCK.

Page 5 of 25 Rev. 25

'Salem I

S1.OP-SO.WG-O0,(Q) 5.2.4 IF Iodine Sampler OR Particulate Sampler is inoperable, THEN ENSURE Chemistry Department is collecting a continuous sample of the effluent release pathway with auxiliary sampling equipment (IAW the ODCM).

5.2.5 IF Plant Vent Flow Rate Monitor is inoperable, THEN ESTIMATE the Plant Vent Flow Rate at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> LAW Attachment 4 and the ODCM.

5.2.6 IF Sampler Flow Rate Monitor is inoperable, THEN ENSURE Chemistry Department is estimating flow rate at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> lAW SC.CH-AB.ZZ-1102(Q) and the ODCM.

5.2.7 PERFORM Pre-Release Verification of 12 GDT Holdup Alignment lAW, Section 1.0.

5.2.8 RECORD the following on Attachment 2:

Section 4.1, Release Verification Section 4.2, Ventilation Configuration Section 4.3, Radiation Monitor Release Data Section 4.4, Release Review 5.2.9 OS/CRS REVIEW AND COMPLETE Attachment 2, Section 4.5.

CAUTION DO NOT release 12WG31, GDT INLET VALVE, until commencing the release.

5.2.10 OBTAIN the CRS Tagging Release for 12WG31.

5.2.11 PERFORM the following preparations at Panel 104-1 for the GDT release:

A. ENSURE 12 GDT is NOT in service.

B.

ENSURE 12 GDT is NOT selected for "Standby".

C.

RECORD 12 GDT "Initial Pressure" (PIS1037) on Attachment 3.

(step continued on next page)

Page 6 of 25 Salem I Rev. 25

Sl.OP-SO WG-0009(o) 5.2.11 (continued)

D. LATCH AND SET 1WG41, GDT VENT CONT VALVE, as follows:

NOTE 1WG41 Controller (1HIC-14) must be set to <0% or 1WG41 will NOT latch.

1.

TURN controller fully counterclockwise until indicator <0%.

2.

POSITION Selector Switch to OPEN AND RELEASE to AUTO position. (Spring return to AUTO).

3.

TURN controller clockwise until indicator _2 100%.

NOTE 1WG41 will begin to open when the indicator is =20%.

4.

ENSURE with Unit 1 Control Room that 1WG41 valve has lost the CLOSED indication AND audible alarm received.

5.

TURN controller fully counterclockwise until indicator < 0%.

6.

ENSURE with Unit 1 Control Room that 1WG41 has closed indication.

E. PERFORM an Independent Verification of the 1WG41 valve position controller, AND RECORD the Independent Verification on Attachment 1, Section 2.0.

F.

NOTIFY Unit 1 Control Room to mark 1R41 and 1R16 Chart Recorders with the following information in preparation for the GDT release:

12 GDT Date/Time RO/PO Initials G. OPEN 12WG31, GDT INLET VALVE.

(step continued on next page)

Page 7 of 25 Rev. 25 sale'm I

Sl.or SO.WG-0009(Q) 5.2.11 (continued)

H.

Slowly OPEN 12WG34.

I..

RECORD Independent Verification (IV) of 12 GDT discharge valves 12WG31 and 12WG34 on Attachment 1, Section 3.0, prior to commencing 12 GDT release.

5.2.12 COMMENCE 12 GDT release as follows:

A. POSITION 1WG41 Selector Switch to OPEN AND RELEASE to AUTO position. (Spring return to AUTO).

B.

SLOWLY SET 1WG41 controller to

• 100% position which corresponds to a maximum release rate of 32 SCFM.

C. PERFORM an Independent Verification of the positioning of 1WG41 on, Section 4.0.

D. RECORD In Progress Release Data on Attachment 2, Section 5.1.

5.2.13 PERFORM the following during 12 GDT release:

NOTE An operator should be stationed at Panel 104-1 to immediately close 12WG34 upon receipt of a High Radiation Alarm or indication of 1WG41 closure.

A. CALCULATE 12 GDT Average Release Rate every 10 minutes on,

AND ADJUST 1WG41 controller position as required based on results.

B.

IF Plant Vent Flow Rate Monitor is inoperable, THEN RECORD Plant Vent Flow Rate Discharge Estimation on at least once every four hours during GDT release.

(step continued on next page)

Page 8 of 25 NOTE While 1WG41 is opening, pressure downstream of 1WG38 will fluctuate between "0" psig and "10" psig until 1WG41 is fully open (100%). Once 1WG41 is fully open, 1WG38 will throttle to maintain <8 psig during the release.

(20016988)

Rev. 25 saldem 1

Si.OP-SO.WG-0009(OJ 5.2.13 (continued)

C.

RECORD Meteorological Data in Attachment 2, Section 5.2.

IF Meteorological Monitor is NOT OPERABLE, THEN NOTIFY the OS/CRS (UFSAR 7.7.2.12).

D.

IF at any time during the release pressure downstream of IWG38 is

> 8.0 psig (1PL8678),

OR 1WG41 CLOSES, THEN TERMINATE the GDT release as follows:

1.

TURN 1WG41 controller fully counter-clockwise until indicator is <0%.

2.

PLACE 1WG41-SWT in CLOSE position, AND ENSURE 1WG41 is CLOSED.

3.

CLOSE 12WG34.

4.

RECORD Final Release Data in Attachment 2, Section 5.3.

5.

INITIATE an Action Request to correct the malfunction.

5.2.14 When 12 GDT pressure = 10 psig OR as directed by OS/CRS, SECURE the GDT release:

A. TURN 1WG41 controller fully counter-clockwise until indicator is

<0%.

B.

PLACE 1WG41-SWT in CLOSE position, AND ENSURE 1WG41 is CLOSED.

C.

CLOSE 12WG34.

D. RECORD Final Release Data in Attachment 2, Section 5.3.

5.2.15 IF GDT release is completed, THEN OPEN 12WG28, 12 Waste Gas Decay Tank Inlet Valve.

5.2.16 IF 1ND17572 - 1WG41 Waste Gas Decay Tank is in BLOCK, THEN PLACE 1ND17572 in NORMAL.

5.2.17 Direct second operator to PERFORM Independent Verification of valves manipulated in this procedure LAW Attachment 1, Section 5.0.

Page 9 of 25 Rev. 25 Salem I

Si.OP-SO.WG-0009(Q) 5.3 Completion and Review 5.3.1 COMPLETE any additional paperwork required by the Chemistry Department AND ATTACH it with this procedure.

5.3.2 COMPLETE Attachment 5, Sections 1.0 and2.0, AND FORWARD this procedure to OS/CRS for review and approval.

5.3.3 OS/CRS PERFORM the following:

A.

COMPLETE Attachment 2, Section 5.4 B.

REVIEW this procedure with Attachments i-5 for completeness and accuracy.

C.

COMPLETE Attachment 5, Section 3.0.

D. FORWARD completed procedure to Technical Supervisor - Chemistry for completion and record retention.

END OF PROCEDURE SECTION Salem 1 Page 10 of 25 Rev. 25

Sl.OP-SO.WG-0009(Q) 6.0 RECORDS 6.1 Retain entire procedure IAW NC.NA-AP.ZZ-0011(Q), Records Management Program.

7.0 REFERENCES

7.1 Salem Generating Station Updated Final Safety Analysis Report:

7.1.1 Section 11.3, Gaseous Waste System 7.1.2 Section 11.4, Radiological Monitoring 7.1.3 Section 9.4, Heating, Ventilation, and Air Conditioning Systems 7.1.4 15.3.6.3, Gas Decay Tank Rupture Analysis 7.2 Technical Specifications - Unit 1:

7.2.1 3.7.7.1 Auxiliary Building Exhaust Filtration System 7.2.2 3.9.12 Fuel Handling Area Ventilation System

7.3 Procedures

7.3.1 NC.NA-AP.ZZ-0020(Q), Control of Nonconforming Components and Structures 7.3.2 SC.OP-AP.ZZ-0102(Q), Use of Procedures 7.3.3 SC.OP-DL.ZZ-0030(Q), Radwaste Monitoring & Control Program 7.3.4 S1.OP-DL.ZZ-0002(Q), Control Room Readings (Modes 5, 6 & Defueled) 7.3.5 Sl.OP-DL.ZZ-0003(Q), Control Room Readings (Modes 1-4) 7.3.6 S1.OP-SO.ABV-0001(Q), Auxiliary Building Ventilation System Operation 7.3.7 S1.OP-SO.CA-0001(Q), Control Air System Operation 7.3.8 S1.OP-SO.CVC-O010(Q), Establishing VCT Atmosphere 7.3.9 Sl.OP-SO.FHV-0001(Q), Fuel Handling Building Ventilation Operation 7.3.10 Si.OP-SO.RM-0001(Q), Radiation Monitoring System Operation 7.3.11 S1.OP-SO.WG-0003(Q), Waste Gas Disposal System Operation 7.3.12 S1.OP-SO.WG-0006(Q), Containment Purge to Plant Vent 7.3.13 S1.OP-SO.WG-0007(Q), Transfer of Waste Gas

7.4 Drawings

7.4.1 203461, No.1 Relay Room Terminal Block Rack 7.4.2 205237, Auxiliary Building - Ventilation 7.4.3 205240, Waste Disposal - Gas 7.4.4 246548, RMS Plant Ventilation Monitor, Flow and Velocity Comparator Page 11 of 25 Rev. 25 Slem 1

S1.OP-SO.WG-0009(Q)

7.5 Others

7.5.1 DCP 1EE-0205, 1WG41 Valve Modification to Mechanically Restrict Flow to *32 SCFM 7.5.2 DCP 1EC-3244, RMS Channel 1R41 Replacement 7.5.3 DE-CB.ABV-0022(Q), Configuration Baseline Documentation for Auxiliary Building Ventilation System 7.5.4 DE-CB.FHV-0021(Q), Configuration Baseline Documentation for Fuel Handling Building Ventilation System 7.5.5 DEF-DES-91-00064, PUP-90-0073 (File: 670), Design Basis for Gaseous Radwaste Release Path Components 1WG41, 1WG38, 2WG41, and 2WG38 7.5.6 PIR 970630118, Independent Verification Missed on Liquid Release.

7.5.7 SER Section 11.0, Radioactive Waste Management 7.5.8 SER Supplement 1, Section 11.0, Radioactive Waste Management 7.5.9 Reg. Guide 1.33, Quality Assurance Program Requirements (Operations) 7.5.10 Reg. Guide 1.21, Measuring, Evaluating and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants 7.5.11 SC-WG001-01, Salem Unit 1, 2 Gas Decay Tank Pressure - Alarm and Recorder (Setpoint Calc & Scaling) 7.5.12 10CFR50, Appendix I 7.5.13 Technical Specification Amendment 234 7.6 Cross

References:

7.6.1 Updated Final Safety Analysis Report:

A.

Section 7.7.2.12, Seismic Monitoring Instrumentation 7.6.2 Technical Specifications - Unit 1:

A. 6.8.4.g - Radiological Effluent Controls Program

7.6.3 Others

A. GL 89-01, Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Offsite Dose Calculation Manual or to the Process Control Program B.

Offsite Dose Calculation Manual Page 12 of 25 Salem1 Rev. 25

Sl.Oi--SO.WG-o009(Q)

7.6.4 Procedures

A. NC.NA-AP.ZZ-0001(Q), Nuclear Procedure System B.

NC.NA-AP.ZZ-001 1(Q), Records Management Program C.

NC.WM-AP.ZZ-0002(Q), Performance Improvement Process D. SC.CH-AB.ZZ-1102(Q), Response to Inoperable Technical Specification Effluent Monitors and Equipment E.

SC.CH-TI.ZZ-0146(Q), Radiological Gaseous Effluent Discharges

7.7 Commitments

7.7.1 C0160 - AR M29-89-124 Quality Assurance Audit Radioactive Effluents and Controls 7.7.2 C0317 - NSO Incident Report 89-679 7.7.3 C0332 - NSO LER 90-016-00 7.7.4 C0333 - NSO LER 88-026-00 Rev. 25 Page 13 of 25 Salem 1

sl.OP-SO.WG-0009(Q)

ATTACHMENT 1 (Page 1 of 2) 12 GAS DECAY TANK ALIGNMENT/VERIFICATION 1.0 PRE - RELEASE ALIGNMENT/VERIFICATION VALVE DESCRIPTION POSITION OPER IV I

RE NO.

INITIALS INITIALS RLA VERIEF 12WG31 GDT INLET V

• CLOSED 12WG32 GDT PRESS TAP OPEN 1 1WG34 GDT STOP TO PLNT V CLOSED 12WG34 GDT STOP TO PLNT V CLOSED 13WG34 GDT STOP TO PLNT V CLOSED 14WG34 GDT STOP TO PLNT V CLOSED 12WG35 GDT STOP V TO HUT CLOSED 12WG28 WG GDT INLET V CLOSED 12WG29 GDT INLET CONT V CLOSED 12WG56 GDT DR V CLOSED 12WG60 N2 SUP TO GDT STOP CLOSED 1WG41 GDT VENT CONT V CLOSED 1WG928 GDT TO VENT HDR CLOSED STOP V 1WG81 WG VENT PRESS TAP OPEN.

12WG131 GDT PRESS TRANS V OPEN

[C0317]

Cleared and Tagged for CRS.

2.0 1WG41 VALVE POSITION CONTROLLER VALVE NO.

DESCRIPTION POSITION IV INITIALS 1WG41 GDT VENT CONT V 0%

Page 14 of 25 Salem I Rev. 25

S1.OP-SO.WG-0009(Q)

ATTACHMENT 1 (Page 2 of 2) 12 GAS DECAY TANK ALIGNMENT/VERIFICATION 3.0 PRE-RELEASE VERIFICATION VALVE NO.

DESCRIPTION POSITION IV INITIALS 12WG31 GDT INLET V OPEN 12WG34 GDT STOP TO PLNT V OPEN 4.0 IN-PROGRESS VERIFICATION VALVE NO.

DESCRIPTION POSITION IV INITIALS 1WG41 GDT VENT CONT V

<*100%

5.0 POST RELEASE VERIFICATION COMPONENT DESCRIPTION POSITION IV INITIALS 12WG28 WG GDT INLET V OPEN 12WG31 GDT INLET V OPEN 12WG34 GDT STOP TO PLNT V CLOSED 1WG41 GDT VENT CONT V CLOSED 1ND17572 1WG41 WASTE GAS DECAY NORMAL TANK Page 15 of 25 Salem I Rev. 25

Si.OP-SO.WG-0009(Q)

ATTACHMENT 2 (Page 1 of 6) 12 GDT RADIOACTIVE GASEOUS RELEASE FORM RELEASE NO.

,; 00Q 1.0 SAMPLE REQUEST (Operations)

S1.1 12 GDT has not been added to since (time)

_/____

(date) 17y

)/*i and is at Z_?....PSIG as indicated by 1PIS1037.

/

1.2 A pre-release sample of 12 GDT and release rate computation is requested.

Signature:

J7

-t*

Date /-Zaf (OS/CRS) 2.0 SAMPLE POINT (Chemistry)

L 2.1 PERFORM gaseous discharge process LAW SC.CH-TI.ZZ-0146(Q),

Radiological Gaseous Effluent Discharges.

f17 2.2 After completion of SC.CH-TI.ZZ-0146(Q), COMPLETE Parts 3.1 through 3.4.

3.0 DOSE, VOLUME ESTIMATES AND APPROVAL (Chemistry)

3.1 Instrumentation

JP INDICATE if the following instruments are in service for release:

INSTRUMENTATION J

IN SERVICE-J Iodine Sampler

__p_

Particulate Sampler Sampler Flow Rate Monitor 7_

Page 16 of 25 Rev. 25 Salem I

ATTACHMENT 2 (Page 2 of 6) 12 GDT RADIOACTIVE GASEOUS RELEASE FORM RELEASE NO. a&V7o -

0 1' 3.0 DOSE, VOLUME ESTIMATES AND APPROVAL (continued)

3.2 Pressure

46 P

COMPLETE the following required data for 12 GDT:

Isolated Pressure Estimated Final Pressure (PSIG)

/0 (PSIG)

Si.OP-SO.WG-0005 (03

3.3 Volume

S*

ESTIMATE total volume of Waste Gas to be released:

S:46--

(CUFT).

Page 17 of 25 NOTE Final pressure is assumed to be 10 PSIG. If maintenance is to be performed and a complete release of tank contents is necessary, then final pressure is assumed to be 0 PSIG.

90 Rev. 25 S"dem

Sl.OP-SO.WG-0009(Q)

ATTACHMENT 2 (Page 3 of 6) 12 GDT RADIOACTIVE GASEOUS RELEASE FORM RELEASE NO.

3.0 DOSE, VOLUME ESTIMATES AND APPROVAL (continued)

3.4 Approval

NOTE Calculated maximum allowable release rate must be >32 SCFM. Tanks with a calculated maximum allowable release rate of _32 SCFM cannot be released.

El' Approval is granted to release 12 GDT at the Calculated Maximum Allowable Release Rate of >,S$O) SCFM.

fP

• This Release is consistent with the Limits set forth in the Offsite Dose Calculation Manual.

NA IF RMS Channel 1R41A or D is inoperable, THEN the following have been completed (LAW the ODCM):

o A. At least two independent samples of 12 GDT contents have been analyzed.

A$

B.

Release rate calculations have been independently verified by at least two technically qualified members of the Facility Staff.

,i_ 1 C. IF RMS Channel 1R16 is inoperable, THEN grab samples are being obtained at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, AND analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

• *IF Iodine Sampler or Particulate Sampler is inoperable, THEN a continuous sample of the effluent release pathway is being collected with auxiliary sampling equipment LAW SC.CH-AB.ZZ-1102(Q), Response to Inoperable Technical Specification Effluent Monitors and Equipment.

S*IF Sampler Flow Rate Monitor is inoperable, THEN flow rate is being estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> LAW SC.CH-AB.ZZ-1102(Q), Response to Inoperable Technical Specification Effluent Monitors and Equipment.

[(T All Chemistry requirements for 12 GDT release to the Plant Vent are satisfied

/a-nda,7th *Iti n given.

Signature:,

/

n gvn Time 1 f'

Date Chemis Y

/*

• FORWARD this Radioactive Gaseous Release Form to OS/CRS.

Page 18 of 25 Rev. 25 Salem1

Si.O'-SO.WG-0009(Q)

ATTACHMENT 2 (Page 4 of 6) 12 GDT RADIOACTIVE GASEOUS RELEASE FORM RELEASE NO.

-o, 4.0 RELEASE REVIEW AND APPROVAL (Operations) 4.1 Release Verification:

• Calculated Maximum Allowable Release Rate from Section 3.4:

SCFM.

EK-Calculated Maximum Allowable Release Rate is > 32 SCFM.

4.2 Ventilation Configuration:

Total number of Auxiliary Total Number of Fuel Handling Pressure Relief Building Exhaust Fans Building Exhaust Fans In In Service In Service Service (Yes/No)

______I I

A10) 4.3 Radiation Monitor Release Data/Source Check/Channel Operable:

Time Date Radiation Monitor Source Check Monitor Prior to Release A/1.

4 1R16 J

PYINOP c._O CPM

/1_

1R41A OP4LjQ

,Ci/cc

/V 1R41D N/A JtCi/sec 4.4 Release Review RO/PO 4.5 All requirements in release of the tank.

OS/CRS Time 6t, 4",

Date Section 3.0 and subsections 4.1 thru 4.4 are met to authorize the Time Date Page 19 of 25 Rev. 25 Sale m 1

Sl.OP-SO.WG-0009(Q)

ATTACHMENT 2 (Page 5 of 6) 12 GDT RADIOACTIVE GASEOUS RELEASE FORM RELEASE NO.

5.0 RELEASE DATA (Operations) 5.1 In Progress Release Data:

Release started:

Time Date Pressure downstream of 1WG38:

1PL8678 PSIG*

Shall be maintained *8.0 psig to ensure GDT release rate *:32 SCFM.

PERFORM an Independent Verification of:

1WG38 pressure (1PL8678)

• 8.0 psig.

IV 1WG41 controller positioned

• 100% (corresponds to a maximum IV gaseous release rate of *532 SCFM).

_Date Time Independent Verifier 5.2 Meteorological Data.

Meteorological conditions at time of Release.

(El. 33' is preferred channel and should be used if available)

Wind Speed MPH at El.

Wind Direction 0 at El.

A T( ('

-33')

C Page 20 of 25 Rev. 25 Salem I

Si.OP-SO.WG-0009(Q)

ATTACHMENT 2 (Page 6 of 6) 12 GDT RADIOACTIVE GASEOUS RELEASE FORM RELEASE NO.

5.0 RELEASE DATA (continued) 5.3 Final Release Data:

TmDaeRadiation Monitor Highest Reading 1PIS1037 Time Date during release 1R16 CPM PSIG 1R41A I

Ci/cc I 1R41D pXi/sec 1 Plant Vent Flow during Release (average):

SCFM 5.4 12 GDT Radioactive Gaseous Release conducted under supervision of:

Date (OS/CRS)

Page 21 of 25 Salem I Rev. 25

Si.OP-SO.WG-0009(Q)

ATTACHMENT 3 (Page 1 of 1) 12 GDT RELEASE RATE CALCULATION Initial Pressure =

psig (1PIS1037)

Average Release Rate = Initial GDT Pressure-GDT Pressure Time (Min)

Maintain Average Release Rate

• 1.0 psig/min by reducing 1WG41 valve position.

Average Release Rate at end of GDT release shall NOT exceed 1.0 psig/min (IAW the ODCM).

Page 22 of 25 Time (Min)

GDT Pressure (psig)

Average Release Rate Initials (psig/min) *

+10

+20

+30

+40

+50

+60

+70

+80

+90

+100

+110

+120

+130

+140

+150

+160

+170

+180 I

Time Rev. 25 Salem 1

si.OP-SO.WG-0009(Q)

ATTACHMENT 4 (Page 1 of 1)

PLANT VENT FLOW RATE DISCHARGE ESTIMATION 1.0 ESTIMATED FLOW RATE NOTE If Plant Vent Flow Rate Monitor is inoperable, Plant Vent Flow Rate shall be estimated at least once per four hours (lAW the ODCM).

AUX BLDG EXHAUST

1. FHB EXHAUST PRESS RELIEF EST. PLANT VENT FANS IN SERVICE FANS IN SERVICE IN SERVICE FLOW RATE 2

1 N

68,540 (SCFM) 2 1

Y 70,940 (SCFM) 2 2

N 78,540 (SCFM) 2 2

Y 80,940 (SCFM) 1.1 IF Plant Vent Flow Rate Monitor is inoperable, THEN RECORD estimated flow rate at least once every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

m DEstimated Time Date Plant Vent Flow Rate SCFM SCFM SCFM SCFM SCFM SCFM Rev. 25 Page 23 of 25 Salem 1

Sl.OP-.O.WG-OOO9(OJ ATIACHMENT 5 (Page 1 of 2)

COMPLETION SIGN-OFF SHEET 1.0 COMMENTS:

(Include procedure deficiencies and corrective actions.)

Rev. 25 Page 24 of 25 Salem 1

si. 3P-SO.WG-0009(oJ ATTACHMENT 5 (Page 2 of 2)

COMPLETION SIGN-OFF SHEET

2.0 SIGNATURES

Print Initials Signature Date INDEPENDENT VERIFICATION:

3.0 OS/CRS FINAL REVIEW AND APPROVAL:

This procedure with Attachments 1-5 is reviewed for completeness and accuracy.

All deficiencies, including corrective actions, are clearly recorded in the COMMENTS Section of this attachment.

Date:

Signature:

(OS/CRS)

Page 25 of 25 Rev. 25 Salem I

NC.TQ-WB.ZZ-031 0(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SALEM STATION:

SYSTEM:

Emergency Plan TASK:

TASK NUMBER:

JPM NUMBER:

Classify an event and complete an ICMF within the regulatory committed time limit (G-ESG-1) 1240020502 GOLF NRC - SROA.4 (ESG-1)

ALTERNATE PATH:

APPLICABILITY:

EO-ROW=

K/A NUMBER:

IMPORTANCE FACTOR:

STA 2.4.38 N/A 4.0 RO SRO SRO EVALUATION SETTING/METHOD:

Simulate (Simulator or Classroom)

REFERENCES:

Salem ECG TOOLS AND EQUIPMENT:

Inform Simulator Operators-DO NOT ERASE ANY PROCEDURES UNTIL THE SRO EVALUATOR APPROVES VALIDATED JPM COMPLETION TIME:

12 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS:

15 minutes APPROVAL:

BARGAINING UNIT REPRESENTATIVE

-TRAININGSUPERVISOR or designee AOPE*AiTIONS CeNAE o r dsig Me CAUTION:

No plant equipment shall be operated during the performance of a JPM without the following:

1. Permission from the OS or Unit CRS;

2. Direct oversight by a qualified individual (determined by the individual granting permission based on plant conditions).

3. Verification of the "as left" condition by a qualified individual.

ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION:

JPM PERFORMED BY:

GRADE: DSAT DUNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE:

DATE:

Rev. 0 Page I of 5 Nuclear Common

NC.TQ-WB.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

Emergency Plan Classify an event and complete an ICMF within the regulatory committed time limit (G-ESG-1)

TASK NUMBER:

1240020502 INITIAL CONDITIONS:

1. You have a maximum of 5 minutes to review the Emergency Operating Procedures used during this scenario to refresh your memory of all events/paths. At the end of your review you will become the Operations Superintendent (OS). Inform the Evaluator when you are ready to assume OS duties.

You may continue to reference the procedures or to look at the control board but "the clock will be running."

INITIATING CUE:

You are the Duty OS. Classify the event, complete the Attachment and provide an ICMF to the Primary Communicator within the required time limit.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Rev. 0 Nuclear Common SYSTEM:

TASK:

Page 2 of 5

NC.TQ-WB.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM:

Emergency Plan TASK:

Classify an event and complete an ICMF within the regulatory committed time limit (G-ESG-1)

STEP STEP COMMENTS NO.

(*Denotes a Critical Step)

STANDARD EVAL (Required for UNSAT

_NO.

(#Denotes a Sequential Step)

SIU evaluation)

Provide candidate with "Tear-off sheet" Reviews initial conditions and EOP's (as necessary - 5 minute limit prior to starting)

• START TIME:

• Start time begins when candidate CUE: The regulatory commitment time reports he/she is ready to assume OS clock has started duties 1

Reviews ECG to classify event NOTE: It is acceptable to use the laminated tables in the simulator, rather than the ECG 2

Classifies the event Determines the classification of the event as an ALERT and refers to ECG J __________

J Fills out Section A of the Attachment

"* Unit: 2

"* EAL#(s): 3.2.2.b

• Time: Current Time 0

0 Date: Today's Date Initials as EC Nuclear Common 3

Rev. 0 Page 3 of 5

NC.TQ-WB.ZZ-031 0(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM:

Emergency Plan TASK:

Classify an event and complete an ICMF within the regulatory committed time limit (G-ESG-1)

STEP STEP COMMENTS NO.

(*Denotes a Critical Step)

STANDARD EVAL (Required for UNSAT

(#Denotes a Sequential Step)

S/U evaluation) 4 Call communicators to the Control Room Pages communicators CUE: I am the Primary Communicator Complete the ICMF CUE: For purposes of the examination, if a release occurred during the event then check the "radiological release in progress" block. The OS would have checked that block if the ECG had been done in real time.

KEY A TTA CHED Provide the ICMF to the Primary Communicator (CM1) and direct the CM1 to implement ECG Attachment 6 Fills out Section I1:

"* *Checks block for the emergency classification

"* Time: Current Time

"* Date: Today's Date

"* EAL#(s): 3.2.2.b

"* *Description of Event: Brief description capturing the major elements Fills out Section III:

• Checks block for no release in progress Fills out Section IV:

CUE: Wind direction is from 2650, 12 mph Initials for approval to transmit Provides ICMF to CM1 within 15 minutes of START TIME COMPLETION TIME:

t

-t Terminating Cue: Repeat back message from the operator on the status of the JPM, and then state "This JPM is complete" Nuclear Common 5

Rev. 0 Page 4 of 5

NC.TQ-WB.ZZ-0310(Z)

INITIAL CONDITIONS:

1. You have a maximum of 5 minutes to review the Emergency Operating Procedures used during this scenario to refresh your memory of all events/paths. At the end of your review you will become the Operations Superintendent (OS). Inform the Evaluator when you are ready to assume OS duties. You may continue to reference the procedures or to look at the control board but "the clock will be running."

INITIATING CUE:

You are the Duty OS. Classify the event, complete the Attachment and provide an ICMF to the Primary Communicator within the required time limit.

Nuclear Common Page 5 of 5

E ('(

ATT 2 Pg 1 of 2 ATTACHMENT 2 ALERT

1.

EMERGENCY COORDINATOR (EC) LOG SHEET Initials A.

DECLARE AN ALERT AT SALEM UNIT C__

EAL# 3.

o2.

• 9 Declared at */*evr "//*

hrs on *V' e '

time date EC B.

NOTIFICATIONS

1.

CALL communicators to the Control Room.

EC

2.

COMPLETE the INITIAL CONTACT MESSAGE FORM (ICMF)

(last page of this attachment).

EC

3.

PROVIDE the ICMF to the Communicator (CM1) and DIRECT the CM1 to implement ECG Attachment 6.

EC

4.

DIRECT the Secondary Communicator (CM2) to implement ECG for an ALERT.

EC

5.

LOCATE the confidential envelope in the Operations Superintendent (O.S.) Desk marked "Emergency Callout". Remove the card that contains the Emergency Callout System activation steps: follow the directions.

When complete return to this procedure.

(EP96-003)

OS

6.

IMPLEMENT EPEP 102 for OS. EDO or ERM.

EC Rev. 03 SGS

ECG ATT 2 Pg. 2 of 2 INITIAL CONTACT MESSAGE FORM I.

THIS IS (NAME)

, COMMUNICATOR EN THE E] CONTROL ROOM 13 TSC AT THE SALEM NUCLEAR GENERATING STATION, UNIT NO.

II.

0 THIS IS NOTIFICATION OF AN ALERT WHICH WAS DECLARED AT C?2eAJT (Time - 24 HR CLOCK)

EAL # £'.

i DESCRIPTION OF EVENT:

ON

/t4 (DATE)

Al 09/,

-A(*z

,..6 O6K/4 /

/_5

/9o4_

III.

~

NO RADIOLOGICAL RELEASE IS IN PROGRESS.

1 see NOTE for release 0

THERE IS A RADIOLOGICAL RELEASE IN PROGRESS.

definition IV.

33 FT. LEVEL WIND DIRECTION (From):

WIND SPEED:

(From MET Computer)

(DEGREES)

(MPH)

V.

NO PROTECTIVE ACTIONS ARE RECOMMENDED AT THIS TIME EC Initials (Approval to Transmit ICMF)

Rev. 03 NOTE:

Radiological Release is defined as: Plant Effluent > Tech Spec Limit of 2.42E+05 pLCi/sec Noble Gas or 2.1E+O1

.+/-Ci/sec 1-131.

SGS

NC.TQ-WB.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SALEM STATION:

SYSTEM:

TASK:

TASK NUMBER:

JPM NUMBER:

Emergency Plan Classify an event and complete an ICMF within the regulatory committed time limit (G-ESG-2) 1240020502 GOLF NRC - SROA.4 (ESG-2)

ALTERNATE PATH:

APPLICABILITY:

EO W

RO =

K/A NUMBER:

IMPORTANCE FACTOR:

STA

=

SRO r-I 2.4.38 N/A 4.0 RO SRO EVALUATION SETTINGIMETHOD:

Simulate (Simulator or Classroom)

REFERENCES:

Salem ECG TOOLS AND EQUIPMENT:

Inform Simulator Operators - DO NOT ERASE ANY PROCEDURES UNTIL THE SRO EVALUATOR APPROVES VALIDATED JPM COMPLETION TIME:

12 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS:

15 minutes APPROVAL:

/

BARGAINING UNIT REPRESENTATIVE

./TRAINING SUPERVISOR or designee 1or desig eeL CAUTION:

No plant equipment shall be operated during the performance of a JPM without the following:

1. Permission from the OS or Unit CRS;

2. Direct oversight by a qualified individual (determined by the individual granting permission based on plant conditions).

3. Verification of the "as left" condition by a qualified individual.

ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION:

JPM PERFORMED BY:

GRADE: D]SAT DUNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE:

DATE:

Rev. 0 Page I of 5 Nuclear Common

NC.TQ-WB.ZZ-031 0(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

Emergency Plan Classify an event and complete an ICMF within the regulatory committed time limit (G-ESG-2)

TASK NUMBER:

1240020502 INITIAL CONDITIONS:

1. You have a maximum of 5 minutes to review the Emergency Operating Procedures used during this scenario to refresh your memory of all events/paths. At the end of your review you will become the Operations Superintendent (OS). Inform the Evaluator when you are ready to assume OS duties.

You may continue to reference the procedures or to look at the control board but "the clock will be running."

INITIATING CUE:

You are the Duty OS. Classify the event, complete the Attachment and provide an ICMF to the Primary Communicator within the required time limit.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Rev. 0 Nuclear Common SYSTEM:

TASK:

Page 2 of 5

NC.TQ-WB.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM:

Emergency Plan TASK:

Classify an event and complete an ICMF within the regulatory committed time limit (G-ESG-2)

STEP STEP COMMENTS NO.

(*Denotes a Critical Step)

STANDARD EVAL (Required for UNSAT

(#Denotes a Sequential Step)

SIU evaluation)

Provide candidate with "Tear-off sheet" Reviews initial conditions and EOP's (as necessary - 5 minute limit prior to starting)

• START TIME:

• Start time begins when candidate CUE: The regulatory commitment time reports he/she is ready to assume OS clock has started duties 1

Reviews ECG to classify event NOTE: It is acceptable to use the laminated tables in the simulator, rather than the ECG 2

Classifies the event Determines the classification of the event as an ALERT and refers to ECG 3

Fills out Section A of the Attachment 0 Unit:2

"* EAL#(s): 3.2.3.a

"* Time: Current Time

"* Date: Today's Date

"* Initials as EC Nuclear Common Rev. 0 Page 3 of 5

NC.TQ-WB.ZZ-031 0(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

Emergency Plan Classify an event and complete an ICMF within the regulatory committed time limit (G-ESG-2)

STEP STEP COMMENTS NO.

(*Denotes a Critical Step)

STANDARD EVAL (Required for UNSAT

(#Denotes a Sequential Step)

S/U evaluation) 4 Call communicators to the Control Room Pages communicators CUE: I am the Primary Communicator Complete the ICMF CUE: For purposes of the examination, if a release occurred during the event then check the "radiological release in progress" block. The OS would have checked that block if the ECG had been done in real time.

KEY A TTA CHED Fills out Section II:

"* *Checks block for the emergency classification

"* Time: Current Time

"* Date: Today's Date

"* EAL#(s): 3.2.3.a

"* *Description of Event: Brief description capturing the major elements Fills out Section III:

• *Checks block for no release in progress Fills out Section IV:

CUE: Wind direction is from 2650, 12 mph Initials for approval to transmit 6

Provide the ICMF to the Primary Provides ICMF to CM1 within 15 minutes of Communicator (CM1) and direct the CM1 START TIME to implement ECG Attachment 6 COMPLETION TIME:

Terminating Cue: Repeat back message from the operator on the status of the JPM, and then state "This JPM is complete" Nurlear Common SYSTEM:

TASK:

5 Page 4 of 5 Rev. 0

NC.TQ-WB.ZZ-031 0(Z)

INITIAL CONDITIONS:

1. You have a maximum of 5 minutes to review the Emergency Operating Procedures used during this scenario to refresh your memory of all events/paths. At the end of your review you will become the Operations Superintendent (OS). Inform the Evaluator when you are ready to assume OS duties. You may continue to reference the procedures or to look at the control board but "the clock will be running."

INITIATING CUE:

You are the Duty OS. Classify the event, complete the Attachment and provide an ICMF to the Primary Communicator within the required time limit.

Nuclear Common Page 5 of 5

es6

-CL ATTACHMENT 2 ALERT I.

EMERGENCY COORDINATOR (EC) LOG SHEET

~Initials A.

DECLARE AN ALERT AT SALEM UNIT EAL#

3-2 O-Declared at6.4C1C r

'/l /ig hrs on /obt i

)4rw)l time date B.

NOTIFICATIONS

1.

CALL communicators to the Control Room.

2.

COMPLETE the INITIAL CONTACT MESSAGE FORM (ICMF)

(last page of this attachment).

3.

PROVIDE the ICMF to the Communicator (CM 1) and DIRECT the CM1 to implement ECG Attachment 6.

4.

DIRECT the Secondary Communicator (CM2) to implement ECG for an ALERT.

5.

LOCATE the confidential envelope in the Operations Superintendent (O.S.) Desk marked "Emergency Callout". Remove the card that contains the Emergency Callout System activation steps, follow the directions.

When complete return to this procedure.

(EP96-003)

6.

IMPLEMENT EPEP 102 for OS, EDO or ERM.

Rev. 03 E ('(;

ATT 2 Pg. 1 of 2 EC EC EC EC EC OS EC SGS

INITIAL CONTACT MESSAGE FORM I.

THIS IS (NAME)

, COMMUNICATOR IN THE 0l CONTROL ROOM OTSC AT THE SALEM NUCLEAR GENERATING STATION, UNIT NO. J-.

II.

o] THIS IS NOTIFICATION OF AN ALERT WHICH WAS DECLARED(AT 6ie

-4 ON OaK),DT (Time - 24 HR CLOCK)

'(DATE)

EAL # 3.

o-3 A-DESCRIPTION OF EVENT:

CAAO AAA.V?'

ol 4agc 7

e

//15 c-C Pe e III [*

NO RADIOLOGICAL RELEASE IS IN PROGRESS.

Isee NOTE m*

for release

[] THERE IS A RADIOLOGICAL RELEASE IN PROGRESS.

definition Pýk EC Initials (Approval to Transmit ICMF)

NOTE:

Radiological Release is defined as: Plant Effluent > Tech Spec Limit of 2.42E+05 ptCi/sec Noble Gas or 2. 1E+01 I Ci/sec 1-13 1.

ECG ATT 2 Pg. 2 of. 2 6ý

-e~v 7-; Is *u(-*

6-IV.

33 FT. LEVEL WIND DIRECTION (From):

--Z5 (From MET Computer)

(DEGREES)

(MPH)

WIND SPEED:

NO PROTECTIVE ACTIONS ARE RECOMMENDED AT THIS TIME V.

Rev. 03 SGS

NC.TQ-WB.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SALEM STATION:

SYSTEM:

TASK:

TASK NUMBER:

JPM NUMBER:

Emergency Plan Classify an event and complete an ICMF within the regulatory committed time limit (G-ESG-3) 1240020502 GOLF NRC - SROA.4 (ESG-3)

ALTERNATE PATH:

APPLICABILITY:

EO-K/A NUMBER:

IMPORTANCE FACTOR:

ROI STA 2.4.38 N/A 4.0 RO SRO SRO EVALUATION SETTING/METHOD:

Simulate (Simulator or Classroom)

REFERENCES:

Salem ECG TOOLS AND EQUIPMENT:

Inform Simulator Operators - DO NOT ERASE ANY PROCEDURES UNTIL THE SRO EVALUATOR APPROVES VALIDATED JPM COMPLETION TIME:

12 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS:

15 minutes APPROVAL:

BARGAINING UNIT REPRESENTATIVE

'AINING SUPERVISOR or designee 0PERATIONS NG or designee CAUTION:

No plant equipment shall be operated during the performance of a JPM without the following:

1. Permission from the OS or Unit CRS;

2. Direct oversight by a qualified individual (determined by the individual granting permission based on plant conditions).

3. Verification of the "as left" condition by a qualified individual.

ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION:

JPM PERFORMED BY:

GRADE:

I SAT

[D UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE:

Nuclear Common Page 1 of 5 DATE:

Rev. 0 Page 1 of 5 Nuclear Common

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM:

Emergency Plan TASK:

Classify an event and complete an ICMF within the regulatory committed time limit (G-ESG-3)

STEP STEP COMMENTS NO.

(*Denotes a Critical Step)

STANDARD EVAL (Required for UNSAT

(#Denotes a Sequential Step)

S/U evaluation)

Provide candidate with "Tear-off sheet" Reviews initial conditions and EOP's (as necessary - 5 minute limit prior to starting)

• START TIME:

• Start time begins when candidate CUE: The regulatory commitment time reports he/she is ready to assume OS clock has started duties 1

Reviews ECG to classify event NOTE: It is acceptable to use the laminated tables in the simulator, rather than the ECG 2

Classifies the event Determines the classification of the event as an SITE AREA EMERGENCY and refers to ECG Attachment 3 3

Fills out Section A of the Attachment Unit: 2

• EAL#(s): 3.1.1.b and 3.2.1.b e Time: Current Time Date: Today's Date Initials as EC Nuclear Common NAME:

DATE:

NC.TQ-WB.ZZ-0310(Z)

Page 3 of 5 Rev. 0

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SYSTEM:

Emergency Plan TASK:

Classify an event and complete an ICMF within the regulatory committed time limit (G-ESG-3)

STEP STEP NO.

(*Denotes a Critical Step)

STANDARD

(#Denotes a Sequential Step) 4 Call communicators to the Control Room Pages communicators CUE: I am the Primary Communicator Complete the ICMF CUE: For purposes of the examination, if a release occurred during the event then check the "radiological release in progress" block. The OS would have checked that block if the ECG had been done in real time.

KEY A TTA CHED Fills out Section I1:

"* *Checks block for the emergency classification

"* Time: Current Time

"* Date: Today's Date

"* EAL#(s): 3.1.1.b and 3.2.1.b

• Description of Event: Brief description capturing the major elements Fills out Section III:

0 *Checks block for no release in progress Fills out Section IV:

CUE: Wind direction is from 2650, 12 mph Initials for approval to transmit

-

I*

evaluation) 6 Provide the ICMF to the Primary Provides ICMF to CM1 within 15 minutes of Communicator (CM1) and direct the CM1 START TIME to implement ECG Attachment 6 COMPLETION TIME:

Terminating Cue: Repeat back message from the operator on the status of the JPM, and then state "This JPM is complete" Nuclear Common NAME:

DATE:

NC.TQ-WB.ZZ-0310(Z) 5 Rev. 0 Page 4 of 5

NC.TQ-WB.ZZ-031 0(Z)

INITIAL CONDITIONS:

1. You have a maximum of 5 minutes to review the Emergency Operating Procedures used during this scenario to refresh your memory of all events/paths. At the end of your review you will become the Operations Superintendent (OS). Inform the Evaluator when you are ready to assume OS duties. You may continue to reference the procedures or to look at the control board but "the clock will be running."

INITIATING CUE:

You are the Duty OS. Classify the event, complete the Attachment and provide an ICMF to the Primary Communicator within the required time limit.

Nuclear Common Page 5 of 5

ECG ATT 3 Pg. 1 of 2 EMERGENCY COORDINATOR (EC) LOG SHEET A.

DECLARE A SITE AREA EMERGENCY AT SALEM UNIT C.

EAL #(s)

" S =c-"/

Declared at Cq~etZeAr h7~

irs on time date B.

NOTIFICATIONS

1.

CALL communicators to the Control Room.

Initials EC OS

2.

COMPLETE the INITIAL CONTACT MESSAGE FORM (ICMF)

(last page of this attachment).

BC

3.

PROVIDE the ICMF to the Communicator (CMl) and DIRECT the CMI to implement ECG Attachment 6.

EC

4.

DIRECT the Secondary Communicator (CM2) to implement ECG for a SITE AREA EMERGENCY.

EC

5.

IF NOT done previously, LOCATE the confidential envelope in the Operations Superintendent (O.S.) Desk marked "Emergency Callout". Remove the card that contains the Emergency Callout System activation steps; follow the directions.

When complete return to this procedure.

(EP96-003)

OS

6.

IMPLEMENT EPEP 102 for OS, EDO or ERM.

EC Rev. 03 SGS ATTACHMENT 3 SITE AREA EMERGENCY

ECG ATT 3 Pg. 2 of 2 INITIAL CONTACT MESSAGE FORM I.

THIS IS (NAME)

, COMMUNICATOR IN THE 0] CONTROL ROOM 0 TSC E] EOF AT THE SALEM NUCLEAR GENERATING STATION, UNIT NO.

S-------------------------------------------------------------------------------------------

II.

13 THIS IS NOTIFICATION OF A SITE AREA EMERGENCY WHICH WAS DECLARED AT 04/M

-4ORL ON (T)

(TIME - 24 HOUR CLOCK)

(DATE)

EAL #(s)

-S z / 6 DESCRIPTION OF EVENT: /zA[ */AIA$

CF-,

Ill.

J9

__NO RADIOLOGICAL RELEASE is IN PROGRESS.

osee reesNOTE El THERE IS A RADIOLOGICAL RELEASE IN PROGRESS.

definition bý1 L571Aýý r

u V.

NO PROTECTIVE ACTIONS ARE RECOMMENDED AT THIS TIME EC Initials (Approval to Transmit ICMF)

NOTE:

Radiological Release is defined as: Plant Effluent > Tech Spec Limit of 2.42E+05 [tCi/sec Noble Gas or 2. 1E+01 I tCi/sec 1-13 1.

IV.

33 FT. LEVEL WIND DIRECTION (From):

(From MET Computer)

(DEGREES)

WIND SPEED:

/1,2.

(MPH)

Rev. 03 SGS

NC.TQ-WB.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE SALEM STATION:

SYSTEM:

TASK:

TASK NUMBER:

JPM NUMBER:

Emergency Plan Classify an event and complete an ICMF within the regulatory committed time limit (G-ESG-SPARE) 1240020502 GOLF NRC - SROA.4 (ESG-SPARE)

ALTERNATE PATH:

APPLICABILITY:

EO-K/A NUMBER:

IMPORTANCE FACTOR:

RO-STA =

SRO EVALUATION SETTING/METHOD:

Simulate (Simulator or Classroom)

REFERENCES:

Salem ECG TOOLS AND EQUIPMENT:

Inform Simulator Operators-DO NOT ERASE ANY PROCEDURES UNTIL THE SRO EVALUATOR APPROVES VALIDATED JPM COMPLETION TIME:

12 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS:

15 minutes APPROVAL:

BARGAINING UNIT REPRESENTATIVE

/TRAINING SUPERVISOR or designee APER "IONS M$AGER or designee CAUTION

No plant equipment shall be operated during the performance of a JPM without the following:

1. Permission from the OS or Unit CRS;

2. Direct oversight by a qualified individual (determined by the individual granting permission based on plant conditions).

3. Verification of the "as left" condition by a qualified individual.

ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION:

JPM PERFORMED BY:

GRADE:

l SAT

] UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE:

DATE:

2.4.38 N/A RO 4.0 SRO Rev. 0 Pagel1 of 5 Nuclear Common

NC.TQ-WB.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

Emergency Plan Classify an event and complete an ICMF within the regulatory committed time limit (G-ESG-SPARE)

TASK NUMBER:

1240020502 INITIAL CONDITIONS:

1. You have a maximum of 5 minutes to review the Emergency Operating Procedures used during this scenario to refresh your memory of all events/paths. At the end of your review you will become the Operations Superintendent (OS). Inform the Evaluator when you are ready to assume OS duties.

You may continue to reference the procedures or to look at the control board but "the clock will be running."

INITIATING CUE:

You are the Duty OS. Classify the event, complete the Attachment and provide an ICMF to the Primary Communicator within the required time limit.

Rev. 0 Nuclear Common SYSTEM:

TASK:

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Page 2 of 5

NC.TQ-WB.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM:

Emergency Plan TASK:

Classify an event and complete an ICMF within the regulatory committed time limit (G-ESG-SPARE)

STEP STEP COMMENTS NO.

(*Denotes a Critical Step)

STANDARD EVAL (Required for UNSAT

(#Denotes a Sequential Step)

S/U evaluation)

Provide candidate with "Tear-off sheet" Reviews initial conditions and EOP's (as necessary - 5 minute limit prior to starting)

• START TIME:

• Start time begins when candidate CUE: The regulatory commitment time reports he/she is ready to assume OS clock has started duties 1

Reviews ECG to classify event NOTE: It is acceptable to use the laminated tables in the simulator, rather than the ECG 2

Classifies the event Determines the classification of the event as an ALERT and refers to ECG 3

Fills out Section A of the Attachment Unit: 2 EAL#(s): 3.2.2.a

• Time: Current Time Date: Today's Date Initials as EC Nuclear Common Page 3 of 5 Rev. 0

NC.TQ-WB.ZZ-0310(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

Emergency Plan Classify an event and complete an ICMF within the regulatory committed time limit (G-ESG-SPARE)

STEP STEP

(*Denotes a Critical Step)

IDenotes a Sequential Step)

Call communicators to the Control Room Complete the ICMF CUE: For purposes of the examination, if a release occurred during the event then check the "radiological release in progress" block. The OS would have checked that block if the ECG had been done in real time.

KEY A TTA CHED Provide the ICMF to the Primary Communicator (CM1) and direct the CM1 to implement ECG Attachment 6 T

I V

STANDARD 9

I Pages communicators CUE: I am the Primary Communicator EVAL SIU COMMENTS (Required for UNSAT evaluation)

+

4 Fills out Section II:

"* *Checks block for the emergency classification

"* Time: Current Time

"* Date: Today's Date

"* EAL#(s): 3.2.2.a

"* *Description of Event: Brief description capturing the major elements Fills out Section III:

• *Checks block for no release in progress Fills out Section IV:

CUE: Wind direction is from 2650, 12 mph Initials for approval to transmit Provides ICMF to CM1 within 15 minutes of START TIME COMPLETION TIME:

Terminating Cue: Repeat back message from the operator on the status of the JPM, and then state "This JPM is complete" Nuclear Common SYSTEM:

TASK:

5 Page 4 of 5 Rev. 0

NC.TQ-WB.ZZ-0310(Z)

INITIAL CONDITIONS:

1. You have a maximum of 5 minutes to review the Emergency Operating Procedures used during this scenario to refresh your memory of all events/paths. At the end of your review you will become the Operations Superintendent (OS). Inform the Evaluator when you are ready to assume OS duties. You may continue to reference the procedures or to look at the control board but "the clock will be running."

INITIATING CUE:

You are the the Primary Duty OS. Classify the event, complete the Attachment and provide an ICMF to Communicator within the required time limit.

Nuclear Common Page 5 of 5

ATTACHMENT 2 ALERT I.

EMERGENCY COORDINATOR (EC) LOG SHEET Initials A.

DECLARE AN ALERT AT SALEM UNIT EAL #

c2-.,) e Declared at(f/,eVPIr *'e hrs on time date B.

NOTIFICATIONS

1.

CALL communicators to the Control Room.

2.

COMPLETE the INITIAL CONTACT MESSAGE FORM (ICMF)

(last page of this attachment).

3.

PROVIDE the ICMF to the Communicator (CM1) and DIRECT the CM1 to implement ECG Attachment 6.

4.

DIRECT the Secondary Communicator (CM2) to implement ECG for an ALERT.

5.

LOCATE the confidential envelope in the Operations Superintendent (O.S.) Desk marked "Emergency Callout". Remove the card that contains the Emergency Callout System activation steps; follow the directions.

When complete return to this procedure.

(EP96-003)

6.

IMPLEMENT EPEP 102 for OS, EDO or ERM.

Rev. 03 4Z ECG ATT 2 Pg. 1 of 2 EC EC EC EC EC OS EC 6 ý ý -

SGS

INITIAL CONTACT MESSAGE FORM I.

THIS IS (NAME)

COMMUNICATOR IN THE 0l CONTROL ROOM E3 TSC AT THE SALEM NUCLEAR GENERATING STATION, UNIT NO. A.

O THIS IS NOTIFICATION OF AN ALERT WHICH WA DECLARED AT aJ'-

1144e ON ILOCA (5 (Time - 24 HR CLOCK)

(DATE)

EAL # 3-2,2 0-DESCRIPTION OF EVENT:

wUIu

(-AA) AJO T QA

Kt,geLsA-

A (A) rA t/A]

>17,

III.

NO RADIOLOGICAL RELEASE IS IN PROGRESS.

see NOTE for release 0

THERE IS A RADIOLOGICAL RELEASE IN PROGRESS.

Jdefinition IV.

33 FT. LEVEL WIND DIRECTION (From):_____

(From MET Computer)

(DEGREES)

WIND SPEED:

/I,?

(MPH)

V.

NO PROTECTIVE ACTIONS ARE RECOMMENDED AT THIS TIME EC Initials (Approval to Transmit ICMF)

Rev. 03 ECG ATT 2 Pg. 2 of 2 I-NOTE:

Radiological Release is defined as: Plant Effluent > Tech Spec Limit of 2.42E+05 PCi/sec Noble Gas or 2.1E+01 jiCi/sec 1-131.

14r 6/ý- 1"eve C--

SGS