Text

Draft - Section a Operating
	ML023290590
Person / Time
Site:	Salem
Issue date:	11/04/2002
From:	Diane Jackson; Public Service Enterprise Group
To:	Conte R; NRC/RGN-I/DRS/OSB
References
	50-272/02-301, 50-311/02-301 50-272/02-301, 50-311/02-301
	Download: ML023290590 (241)
	v • d • e

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

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Administrative Section Examination TASK: Perform a peer check on a completed ECP TASK NUMBER: 1200020301 JPM NUMBER: 2002 GOLF NRC RO Al ALTERNATE PATH: K/A NUMBER: 2.1.25 IMPORTANCE FACTOR: 2.8 3.1 APPLICABILITY: RO SRO EO = RO Ej STA = SRO L--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 TRAINING SUPERVISOR OPERATIONS MANAGER REPRESENTATIVE 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: N/A Minutes JPM PERFORMED BY: GRADE: FISAT r UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Nuclear Common Page I of 6 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 TASK NUMBER: 1200020301 INITIAL CONDITIONS:

Unit 2 is in HSB at 547°F/2235 PSIG with a reactor startup planned for this shift.

Previous Critical Conditions:

0 Reactor trip after 55 days at 100% power 0 600 ppm Boron 0 13000 MWD/MTU 0 Bank D @ 217 steps Intended Critical Conditions:

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after the trip

Bank D @ 95 steps SIMULATOR SETUP:

N/A INITIATING CUE:

Perform a peer check on a manual ECP.

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 6 Rev. 0

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

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE 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)

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:

1 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 pcm.

Power in 1.2 (100%) and Boron Concentration in 1.3 (600 ppm).

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

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE 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 4.3 Xenon Reactivity at Time in 1 .1 (48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 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 0.26 hours 0.00155 weeks 3.557675e-4 months 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-85). 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 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

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

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%

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

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE 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 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) (-700) + (1880) + (2000) + (-83) =

+2943 to +3251 pcm Review Section 7.0 - INTENDED TERMINATE JPM CRITICAL BORON CONCENTRATION DETERMINATION STOP TIME:

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

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

INITIAL CONDITIONS:

Unit 2 is in HSB at 547°F/2235 PSIG with a reactor startup planned for this shift.

Previous Critical Conditions:

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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after the trip

Bank D @ 95 steps INITIATING CUE:

Perform a peer check on a manual ECP.

Nuclear Common Page 6 of 6

P SEG Internal Use Only / "

PSEG NUCLEAR L.L.C.

SALEM GENERATING STATION/REACTOR ENGIrp*g SC.RE-RA.ZZ-0001(Q) - REV. 0 ESTIMATED CRITICAL POSITION CONTR 0 USE CATEGORY: I COPY # /

REVISION

SUMMARY

Biennial Review performed: Yes X No NA This revision combined procedures S .RE-RA.ZZ-0001 (Q) and S2.RE-RA.ZZ-000 I(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 /Ii IA,1 APPROVED:

Manager Nuclear Fuels/Reactor Engineering (or Designee) Date

PSEG Internal Use Only Page 2 of 2 SC.RE-RA.ZZ-0001(Q) - REV. 0 ESTIMATED CRITICAL POSITION Step 3.11 -:thevalue 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.I.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 5.1.1 .D.4.a - changed from "use 588 pcm" to "use Figures 10 A, B, C of S 1(2).RE RA.ZZ-0012(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 100" 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- 11. 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.

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

ESTIMATED CRITICAL POSITION TABLE OF CONTENTS Section Title Page 1.0 P U R PO SE ....................................................................................................... 2 2.0 PREREQUISITES ............................................................................................ 2 3.0 PRECAUTIONS AND LIMITATIONS ......................................................... 2 4.0 EQUIPMENT/MATERIAL REQUIRED ....................................................... 4 5.0 PROCEDURE ................................................................................................ 4 5.1 Estimated Critical Position ................................................................. 4 5.2 Completion and Review ..................................................................... 10 6.0 RE C O RD S .................................................................................................... 11

7.0 REFERENCES

.............................................................................................. 11 ATTACHMENTS Estimated Critical Position Work Sheet ........................................................ 12 Completion Sign-Off Sheet ............................................................................ 18 Salem Common Page 1 of 18 Rev. 0

SC.RE-RA.ZZ-OOOI(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 4.1.1.1.1.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 2.1 The plant is in hot standby (Tave = 5470 F).

3.0 PRECAUTIONS AND LIMITATIONS 13.1 The NAME, INITIALS, and SIGNATURES of all personnel performing steps in this procedure, and the DATE of performance shall be recorded on Attachment 2.

-n 3.2 Conditional steps shall be evaluated by the user and if not applicable marked "N/A." Conditional steps include words IF, WHEN, and OR 3.3 All deficiencies and corrective actions taken during the performance of this procedure, including Termination, shall be documented in the Comments section of Attachment 2.

(* 3.4 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.

3.5 The critical control rod position shall be above the hot zero power minimum 7j- insertion limit of the Core Operating Limits Report (COLR) IAW T/S 3.1.3.5.

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

& 3.7 Criticality must be anticipated any time there is an insertion of positive reactivity (e.g. RCCA withdrawal, Boron Dilution, etc.).

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

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 3.9 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, THEN a new estimated critical position shall be calculated.

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

S3.13 All previous critical data should be from the same point in time. This is especially pertinent for data collected during transients. [C0498]

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.

3.15 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.

,31 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.

~(A~i7 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.

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sC.RE-RA.ZZ-OOOI(Q) 4.0 EQUIPMENT/MATERIAL REQUIRED Calculator Approved Computer Code 5.0 PROCEDURE NOTE If available, consider using the Power Distribution Monitoring System (PDMS) IAW SC.RE SO.NIS-0001(Q), BEACON Operation & Calculation Verification, to satisfy the requirements of this procedure.

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

A. DETERMINE appropriate Previous Critical Conditions: [C04981 CHOOSE the best conditions available, not necessarily the 9&-. 2.

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 K 3. 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.

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

OBTAIN Date, Time, Power Level, Boron Concentration,

- and Control Bank position data from any of the following

?dL--A5 sources:

, Control Room Logs

Calonme ic alculations

Past ECPs

Control Room Charts

Chemistry Logs

Power Distribution Monitoring System (PDMS)

6. OBTAIN Cycle Exposure data

?tý- B. OBTAIN Shutdown Conditions from any of the following sources:

(trolRoo m Logs)

Control Room Charts

Shutdown Margin Calculations

+ Power Distribution Monitoring System (PDMS)

T UA /C. DETERMINE Intended Critical Conditions: I CHOOSE a Date and Time that is within four hours prior to achieving criticality IAW 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 stepsOL 90-130steps' and EOL 125-145 steps).

This ensures adequate control rod height for AF control an should be consistently greater than 500-pcm rod height. .6-7 CHOOSE a Control Bank Position that allows for the full

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

OBTAIN Cycle Exposure data.

Salem Common Page 5 of 18 Rev. 0

sC.RE-RA.ZZ-0001(Q) tD DETERMINE Reactivity Worths at Previous Critical Conditions:

OBTAIN Integral Rod Worth from any of the following sources:

le* f SI (2).RE-RA.ZZ-0012(Q), Figures (use

Advanced Nodal Code (ANC)

Nuclear Design Report (NDR) 99 4-2 OBTAIN Power Defect from any of the following sources:

* ~f Sl(2).RE-RA.ZZ-0012(Q), Figures

A-idvaced Nodal Code (ANC)

Nuclear Design Report (NDR) qf -&3. OBTAIN Xenon Reactivity from an applicable source:

equilibrium xenon conditions existed SIF previous critical conditions, THEN use(igure 6 f Si (2).RE-RA.ZZ-0012(Q).

_/4 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)

A 4. OBTAIN Samarium Reactivity from an applicable source:

IF equilibrium samarium conditions ex pre .ous critical conditions, THEN us FZigure 10 A, B C of S1(2).RE-RA.ZZ-0012(Q), F -

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

b. 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)

Nuclear Design Report (NDR)

4A.*E. DETERMINE Reactivity Worths at Intended Critical Conditions:

.A . OBTAIN Integral Rod Worth from any of the following sources:

(ef SI(2).RE-RA.ZZ-0012(Q), Figures (use

Advanced Nodal Code (ANC)

Nuclear Design Report (NDR) 4 -&/2. OBTAIN Xenon Reactivity from an applicable source:

a.* IF the shutdown was due to a reactor trip and equilibrium xenon condi iste.4rior to the reactor trip, THEN us igure 8 Cof S 1(2).RE-RA.ZZ-00 12(Q), iigures.

b. 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)

Nuclear Design Report (NDR)

( & 3. OBTAIN Samarium Reactivity from an applicable source:

a. IF equilibrium samarium condit stedAt the time of shutdown, THEN us 10 BC of S1( 2).RE-RA.ZZ-0--2-Q), F i~g --.

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

IF the shutdown was NOT due to a reactor trip OR

_ b. 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)

.-!F. CALCULATE Reactivity Changes and SUM as directed on Attachment 1, Steps 6.1 - 6.5.

G. DETERMINE Intended Critical Boron Concentration: 1C04981 c2LC~ OBT*OT4 RO Equilibrium Boron Concentrations fron=Figure3 0f S(2).RE-RA.ZZ-0012(Q), Figures.

j 2. CALCULATE the Corrected Previous Boron Concentration (due to burnup differences between the previous and intended critical conditions) as directed on Attachment 1, Step 7.1.

3. OBTAIN Differential Boron Worths from any of the following sources:

F ig e! f SI (2).RE-RA.ZZ-0012(Q), Figures

Figure 13 of S1(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.

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

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

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

(L JH. DETERMINE Limits on Intended Critical Control Rod Position:

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

S Fu f S 1(2).RE-RA.ZZ-0012(Q), Figures S eSale-m

(2) Core Operating Limits Report (COLR)

Figure 1 (T/S 3.1.3.5)

CVA 2. OBTAIN Control Bank Positions from either of the following sources for Attachment 1, Steps 8.2 through 8.8:

S iý 4f SI (2).RE-RA.ZZ-0012(Q), Figures S Nuc-ear Design Report (NDR) 5.1.2 USE a different methodology to CALCULATE a second Estimated Critical Position IAW with Step 5.1.1.

5.1.3 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.

5.1.4 COMPLETE Attachment 2, Section 1.0 and 2.0.

5.1.5 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 Attachment 1.

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.

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sC.RE-RA.ZZ-OOO1(Q) 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 Attachment 2, Section 4.0.

END OF PROCEDURE SECTION Salem Common Page 10 of 18 Rev. 0

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

Attachment I

Attachment 2

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 I(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. Si (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-0001(Q)

ATTACHMENT 1 ESTIMATED CRITICAL POSITION WORKSHEET Page 1 of 6 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.

1.0 PREVIOUS CRITICAL CONDITIONS 1.1 Date: t*J Time :,*vpn9r q75 Acu/*

1.2 Power Level _____%RTP 1.3 Boron Concentration M&O1 ppm 1.4 Control Bank Position Bank C 22*9' steps Bank D stps 1.5 Cycle Exposure ___ ____M I/MTU 2.0 SHUTDOWN CONDITIONS 2.1 Reactor Trip Date -X~'~ Time /r?!A4c OR Orderly Shutdown Date 4/4V1 Time A'/

Approximate Shutdown Rate A'A/o %/min 2.2 Power Level Prior to Shutdown %RTP 3.0 INTENDED CRITICAL CONDITIONS 3.1 Date fY Time " il4*bi 3.2 Control Bank Position Bank C 225 steps Bank D q*f steps 3.3 Cycle Exposure /23 d16O MWD/MTU Salem Common Page 12 of 18 Rev. 0

sC.RE-RA.ZZ-O00 I(Q)

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 0 pcm 4.2 Power Defect at Power in (1.2) and Boron f Concentration in (1.3) (+) pcm 4.3 Xenon Reactivity at Time in (1.1) (-) ,*2 pcm NOTE If previous conditions were steady state, use Figure 10 A, B, C.

4.4 Samarium Reactivity at Time in (1.1) (-) V--__" pcm 5.0 REACTIVITY WORTHS AT INTENDED CRITICAL CONDITIONS 5.1 Integral Rod Worth at Position in (3.2) (+) Y (6/ pcm 5.2 Xenon Reactivity 5.2.1 Elapsed Time from (2.1) to (3.1) _ 11f hrs 5.2.2 Xenon Reactivity at Time in (5.2.1) and Power in (2.2) (-___Z_ _ pcm 5.3 Samarium Reactivity 5.3.1 Elapsed Time from (2.1) to (3.1) _ _ _ hrs 5.3.2 Samarium Reactivity at Time in (5.3.1) and Power in (2.2) (-) pcm Salem Common Page 13 of 18 Rev. 0

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

ATTACHMENT 1 ESTIMATED CRITICAL POSITION WORKSHEET Page 3 of 6 6.0 REACTIVITY CHANGES AND SUM 6.1 Integral Rod Worth (4.1)-(5.1) 0 7 5(

Zee -- pcm 6.2 Power Defect (4.2) _____ pcm 6.3 Xenon Reactivity (5.2.2)-(4.3) 52-7 "-.252: "- ý&2pcm 6.4 Samarium Reactivity (5.3.2)-(4.4) // - ____5_____ pcm 6.5 SUM (6.1)+(6.2)+(6.3)+(6.4) _--_- _ pcm 4- /

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 Burnup in (1.5) i.) ppm 7.1.2 HFP ARO Equilibrium Poison Boron Concentration at Burnup in (3.3) ('t 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) ro - __ ______ 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=5470 F

pcm/ppm 7.2.2 Boron Concentration Change .

(6.5)+(7.2.1) - 75 ppm

-- 9 Salem Common Page 14 of 18 Rev. 0

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

ATTACHMENT 1 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 2- ppm

~7, 7.3.2 Differential Boron Worth at Concentration in (7.3.1) and Burnup in (3.3) for Tavg=547°F pcmlppm 7.3.3 Boron Concentration Change (6.5)-(7.3.2) 1--7" 1/ ppm 7.4 Intended Critical Boron Concentration ,-' 4 (7.1.4)-(7.3.3) .- 90

/ ,, 7 ppm 8.0 LIMITS ON INTENDED CRITICAL CONTROL ROD POSITION 8.1 Rod Insertion Limit (TS 3.1.3.5) Bank C 5T steps 8.2 Intended Position + 1000 pcmQ266(Mode 2) 8.2.1 Integral Rod Worth (5.1) + 1000 / ' pcm 8.2.2 Control Bank Position at Worth in (8.2.1) Bank C aY-) steps Bank D 6 steps 8.3 Intended Position + 500 pcm 8.3.1 Integral Rod Worth (5.1) + 500 / 2-'442 pcm 8.3.2 Control Bank Position at Worth in (8.3.1) Bank C /* ) steps Bank D ". -- steps 8.4 Intended Position + 400 pcm 8.4.1 Integral Rod Worth (5.1) + 400 ______pcm 8.4.2 Control Bank Position at Worth in (8.4.1) Bank C steps Bank D _ steps Salem Common Page 15 of 18 Rev. 0

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

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 lclw pcm 8.5.2 Control Bank Position at Worth in (8.5.1) Bank C __ _ -_ steps Bank D -- " steps 8.6 Intended Position - 300 pcm 8.6.1 Integral Rod Worth (5.1) - 300 166d pcm 8.6.2 Control Bank Position at Worth in (8.6.1) Bank C _ -_ _ steps Bank D /"2- steps 8.7 Intended Position - 400 pcm 8.7.1 Integral Rod Worth (5.1) - 400 366T pcm 8.7.2 Control Bank Position at Worth in (8.7.1) Bank C Z2' steps Bank D /

steps 8.8 Intended Position - 500 pcm 8.8.1 Integral Rod Worth (5.1) - 500 2Iee pcm 8.8.2 Control Bank Position at Worth in (8.8.1) BankD 4ý,S steps Time______

Completed By: Date _____ivl Verified By: Date Time Approved By: Date Time Supervisor - Rx. Eng.

Reviewed By: Date Time OS/CRS Salem Common Page 16 of 18 Rev. 0

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

ATTACHMENT 1 ESTIMATED CRITICAL POSITION WORKSHEET Page 6 of 6 9.0 CONFIGURATION AT 10-8 AMPS 9.1 Date Time 9.2 Boron Concentration RCS ppm PZR ppm 9.3 Control Bank Position 9.3.1 Actual Position Bank C steps Bank D steps 9.3.2 Minimum Position (8.1) Bank C steps 9.3.3 Maximum Position (8.8.2) Bank D steps Completed By: Date Time Reviewed By: Date Time OS/CRS Salem Common Page 17 of 18 Rev. 0

sC.RE-RA.ZZ-0001(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

J ame (Print) 6 t, q2- /

54na e!,,,!

?; Y-51;(

Date

.2sDn19/

3.0 INDEPENDENT VERIFICATION:

Name (Print) Initials Signature Date 4.0 FINAL REVIEW AND APPROVAL:

This procedure with Attachments I 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

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

( /7K/'/'1 /21 SALEM GENERATING STATION/REACTOR ENGlrt$kgiII SC.RE-RA.ZZ-0001(Q) - REV. 0 ESTIMATED CRITICAL POSITION CONTh*Ou USE CA'TEGORY: I COPY 7It-REVISION

SUMMARY

Biennial Review performed: Yes X No NA This revision combined procedures S1.RE-RA.ZZ-0001 (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 I__l.____

APPROVED:

Manager Nuclear Fuels/Reactor Engineering (or Designee) Date

PSEG Internal Use Only Page 2 of 2 SC.RE-RA-ZZ-0001(Q) - REV. 0 ESTIMATED CRITICAL POSITION Step 3.11 -the value was changed from 50 pcm to 100 pcm to allow greater flexibility.

Thbe 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 5.1.1 .D.4.a - changed from "use 588 pcm" to "use Figures 10 A, B, C of S 1(2).RE RA.ZZ-0012(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- 11. 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.

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

ESTIMATED CRITICAL POSITION TABLE OF CONTENTS Section Title Page 1.0 P UR P O SE ........................................................................................................ 2 2.0 PREREQUISITES ........................................................................................... 2 3.0 PRECAUTIONS AND LIMITATIONS ......................................................... 2 4.0 EQUIPMENT/MATERIAL REQUIRED ...................................................... 4 5.0 PROCEDURE .................................................................................................. 4 5.1 Estimated Critical Position .................................................................. 4 5.2 Completion and Review ..................................................................... 10 6.0 RECORDS .................................................................................................... 11

7.0 REFERENCES

.............................................................................................. 11 ATTACHMENTS Estimated Critical Position W ork Sheet ....................................................... 12 Completion Sign-Off Sheet ............................................................................ 18 Salem Common Page I of 18 Rev. 0

-C.RE-RA.ZZ-0001(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 4.1.1.1.1.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 LAW SC.RE-IO.ZZ-0002(Q), Low Power Physics Testing and Power Ascension.

2.0 PREREQUISITES 2.1 The plant is in hot standby (Tave = 5470 F).

3.0 PRECAUTIONS AND LIMITATIONS 3.1 The NAME, INITIALS, and SIGNATURES of all personnel performing steps in this procedure, and the DATE of performance shall be recorded on Attachment 2.

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

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

4z*3.4 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.

(Lz'3.5 The critical control rod position shall be above the hot zero power minimum insertion limit of the Core Operating Limits Report (COLR) 1AW T/S 3.1.3.5.

-,(.c"3.6 This procedure does not correct for temperatures other than 547*F.

,*,,*3.7 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.RE-RA.ZZ-OOO1(Q)

A-,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. [C0498]

t*'/--3.9 The actual critical configuration shall be within +/- 1000 pcm of the estimated configuration.

__ 3.10 Chemical analysis is used to verify boron concentrations.

& 3.11 IF the estimated time of criticality changes such that the amount of reactivity change introduced is greater than +/-100 pcm, THEN a new estimated critical position shall be calculated.

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

C/GY.3.14 All previous critical data should be from the same point in time. This is especially pertinent for data collected during transients. [C0498]

13.14 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 1 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.

-*3.16 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.

6c-317 For transient xenon conditions, increased accuracy may be obtained by interpolating between Figures 12 and 13 of S 1(2).RE-RA.ZZ-0012(Q), Figures.

Salem Common Page 3 of 18 Rev. 0

SC.RE-R X.ZZ-OOO1(Q) 4.0 EQUIPMENT/MATERIAL REQUIRED Calculator Approved Computer Code 5.0 PROCEDURE NOTE If available, consider using the Power Distribution Monitoring System (PDMS) LAW SC.RE SO.NIS-0001(Q), BEACON Operation & Calculation Verification, to satisfy the requirements of this procedure.

5.1 Estimated Critical Position

'SC/5.1.1 COMPLETE Attachment 1, Estimated Critical Position Worksheet, Steps 1.1 - 8.8.2 as follows: I A. DETERMINE appropriate Previous Critical Conditions: [C04981 I CHOOSE the best conditions available, not necessarily the

21. 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

'X 3.

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 Page 4 of 18 Rev. 0

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

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

*Control Room Logs-'

¢Calonme ic a culations

Past ECPs

Control Room Charts

Chemistry Logs

Power Distribution Monitoring System (PDMS)

S6. OBTAIN Cycle Exposure data L B. OBTAIN Shutdown Conditions from any of the following sources:

Control Room Charts

Shutdown Margin Calculations

Power Distribution Monitoring System (PDMS)

Cj C. DETERMINE Intended Critical Conditions:

>fL&zi. 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 stepsrMOL 90-130steps and EOL 125-145 steps).

This ensures adequate control rod height for AF--control an -should be consistently greater than 500-pcm rod height. . - ý s-CHOOSE a Control Bank Position that allows for the full

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

OBTAIN Cycle Exposure data.

'A'/3.

9ý4-Salem Common Page 5 of 18 Rev. 0

sC.RE-RA.ZZ-OOO (Qý (LC,/D. DETERMINE Reactivity Worths at Previous Critical Conditions:

tC* w1. OBTAIN Integral Rod Worth from any of the following sources:

tgp of Si (2).RE-RA.ZZ-0012(Q), Figures (use

Advanced Nodal Code (ANC)

Nuclear Design Report (NDR)

OBTAIN Power Defect from any of the following sources:

Figure2f S I (2).RE-RA.ZZ-0012(Q), Figures

A vV"ed Nodal Code (ANC)

Nuclear Design Report (NDR)

(--3. OBTAIN Xenon Reactivity from an applicable source:

-a. IF equilibrium xenon conditions existed previous critical conditions, THEN use igre Of Si (2).RE-RA.ZZ-0012(Q).

/4/ 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 ex previ~ous critical conditions, THEN us Figure 10 A, B C of S1(2).RE-RA.ZZ-0012(%Q), Fi Salem Common Page 6 of 18 Rev. 0

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

b. 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)

Nuclear Design Report (NDR) j *.E. DETERMINE Reactivity Worths at Intended Critical Conditions:

OBTAIN Integral Rod Worth from any of the following sources:

iue4XfSI(2).RE-RA.ZZ-0012(Q), Figures (use Advanced Nodal Code (ANC)

Nuclear Design Report (NDR)

<;d&L--. OBTAIN Xenon Reactivity from an applicable source:

ia. IF the shutdown was due to a reactor trip and equilibrium xenon condi isteArior to the reactor trip, THEN usigure 8J C of S 1(2).RE-RA.ZZ-0012(Q), Figures.

0_%/q b. 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)

+ Nuclear Design Report (NDR)

3. OBTAIN Samarium Reactivity frm an applicable source:

a. IF equilibrium samarium condi *stedtthe time of shutdown, THEN us.A Fige 10. *. / C of S1(2).RE-RA.ZZ-0012(), Fig."z-"

Salem Common Page 7 of 18 Rev. 0

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

b. 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)

~L F. CALCULATE Reactivity Changes and SUM as directed on Attachment 1, Steps 6.1 - 6.5.

"G. DETERMINE Intended Critical Boron Concentration: [C04981

'/. OBT4I-40-ARO Equilibrium Boron Concentrations fro =Figue3 bf S1(2).RE-RA.ZZ-0012(Q), Figures.

/2. CALCULATE the Corrected Previous Boron Concentration (due to burnup differences between the previous and intended critical conditions) as directed on Attachment 1, Step 7.1.

3. OBTAIN Differential Boron Worths from any of the it following sources:

+ e:l26f S 1(2).RE-RA.ZZ-001 2(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.

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

,C */d. CALCULATE the Intended Critical Boron Concentration as directed on Attachment 1, Step 7.4.

Salem Common Page 8 of 18 Rev. 0

sC.RE-RA.ZZ-0001(Q) yZ /H. DETERMINE Limits on Intended Critical Control Rod Position:

U 3L"21. OBTAIN the Rod Insertion Limit for 0% RTP from either of the following sources for Attachment 1, Step 8.1:

S F re:14of Si (2).RE-RA.ZZ-0012(Q), Figures

Sa em (2) Core Operating Limits Report (COLR)

Figure 1 (T/S 3.1.3.5)

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

Figre f Si (2).RE-RA.ZZ-0012(Q), Figures

Nucef-ar Design Report (NDR) 5.1.2 USE a different methodology to CALCULATE a second Estimated Critical Position IAW with Step 5.1.1.

5.1.3 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.

5.1.4 COMPLETE Attachment 2, Section 1.0 and 2.0.

5.1.5 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 I 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 Attachment 1.

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

sC.RE-RA.Z-OOO1(Q) 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 Attachment 2, Section 4.0.

END OF PROCEDURE SECTION Salem Common Page 10 of 18 Rev. 0

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

4 Attachment I

+ Attachment 2

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. S1(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-OOOI(Q)

ATTACHMENT 1 ESTIMATED CRITICAL POSITION WORKSHEET Page 1 of 6 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.

EEWEMNý 1.0 PREVIOUS CRITICAL CONDITIONS 1.1 Date: . Time *,(7) , G./

1.2 Power Level _A____%RTP 1.3 Boron Concentration 6cc ppm 1.4 Control Bank Position Bank C 22 steps Bank D -L7 steps 1.5 Cycle Exposure I*3f6 ,"MWD/MTU 2.0 SHUTDOWN CONDITIONS 2.1 Reactor Trip Date Time ,7"( t9I A4/c&'

Orderly Shutdown Date Time /,

Approximate Shutdown Rate A'i,/42 %/min 2.2 Power Level Prior to Shutdown /6' %RTP 3.0 INTENDED CRITICAL CONDITIONS 3.1 Date 3.2 Control Bank Position Bank C 2-2,3 steps Bank D 95__ steps 3.3 Cycle Exposure /2 47C MWD/MTU Salem Common Page 12 of 18 Rev. o

sC.RE-RA.ZZ-O00 I(Q)

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) H 6' pcm 4.2 Power Defect at Power in (1.2) and Boron ,

Concentration in (1.3) (+) pcm 4.3 Xenon Reactivity at Time in (1.1) (-)__.__ ,__pcm NOTE If previous conditions were steady state, use Figure 10 A, B, C.

4.4 Samarium Reactivity at Time in (1.1) (-) 7.-*-> pcm 5.0 REACTIVITY WORTHS AT INTENDED CRITICAL CONDITIONS 5.1 Integral Rod Worth at Position in (3.2) ( *66 pcm 5.2 Xenon Reactivity 5.2.1 Elapsed Time from (2.1) to (3.1) ____" 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) ____ hrs 5.3.2 Samarium Reactivity at Time in (5.3.1) and Power in (2.2) (-) /&'/O pcm Salem Common Page 13 of IS Rev. 0

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

ATTACHMENT 1 ESTIMATED CRITICAL POSITION WORKSHEET Page 3 of 6 6.0 REACTIVITY CHANGES AND SUM 6.1 Integral Rod Worth (4.1)-(5.1) C _________ pcm 6.2 Power Defect (4.2) __ ,_"__" pcm 6.3 Xenon Reactivity (5.2.2)-(4.3) 5'2-5" - 25>'5: - Z pcm 6.4 Samarium Reactivity (5.3.2)-(4.4) /l/e .1- t1 5" pcm 6.5 SUM (6.1)+(6.2)+(6.3)+(6.4) 7-- pcm / 7 7.0 INTENDED CRITICAL BORON CONCENTRATION DETERMINATION ' '-7 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 Burnup in (1.5) ppm 7.1.2 HFP ARO Equilibrium Poison Boron Concentration at Burnup in (3.3) *'A) 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) 0 Cc - 0 _ ____ 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 f pcm/ppm 7.2.2 Boron Concentration Change -

(6.5)--(7.2.1) -- __7.____ppm Salem Common Page 14 of 18 Rev. o

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

ATTACHMENT 1 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 I 2-t& -92 I/a' C -

"Sý-/ ppm 7.3.2 Differential Boron Worth at Concentration in (7.3.1) and Burnup in (3.3) for Tavg=547°F - *g-, / pcm/ppm 7.3.3 Boron Concentration Change (6.5)-(7.3.2) 9/ ppm 7.4 Intended Critical Boron Concentration

-A' I/

(7.1.4)-(7.3.3) 6c Y,- e/ -_._'__ ppm 8.0 LIMITS ON INTENDED CRITICAL CONTROL ROD POSITION 8.1 Rod Insertion Limit (TS 3.1.3.5) Bank C - steps 8.2 Intended Position + 1000 pcm (Mode 2)

'26el 8.2.1 Integral Rod Worth (5.1) + 1000 pcm 8.2.2 Control Bank Position at Worth in (8.2.1) Bank C C9 steps Bank D C steps 8.3 Intended Position + 500 pcm 8.3.1 Integral Rod Worth (5.1) + 500 / 26&9 pcm 8.3.2 Control Bank Position at Worth in (8.3.1) Bank C /6" steps Bank D steps 8.4 Intended Position + 400 pcm 8.4.1 Integral Rod Worth (5.1) + 400 pcm 8.4.2 Control Bank Position at Worth in (8.4.1) Bank C 2 Q/ steps Bank D S steps Salem Common Page 15 of 18 Rev. 0

sC.R-E-RA.1Z-OOOI(Q)

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 ____-__ pcm 8.5.2 Control Bank Position at Worth in (8.5.1) BankC __ _,_ _ steps Bank D - -_____ steps 8.6 Intended Position - 300 pcm 8.6.1 Integral Rod Worth (5.1) - 300 1(6*f pcm 8.6.2 Control Bank Position at Worth in (8.6.1) Bank C -Z steps Bank D 1,*ý- steps 8.7 Intended Position - 400 pcm 8.7.1 Integral Rod Worth (5.1) - 400 3(6 pcm 8.7.2 Control Bank Position at Worth in (8.7.1) BankC Z-f> steps Bank D /_ _ steps 8.8 Intended Position - 500 pcm 8.8.1 Integral Rod Worth (5.1) - 500 _______pcm 8.8.2 Control Bank Position at Worth in (8.8.1) Bank D /____ steps ite / /7t,/

-,9 Time _______

Completed By: 6 , D Verified By: D_ite Time Approved By: ate Time Supervisor - Rx. Eng.

Reviewed By: Date Time OS/CRS Salem Common Page 16 of 18 Rev. 0

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

ATTACHMENT 1 ESTIMATED CRITICAL POSITION WORKSHEET Page 6 of 6 9.0 CONFIGURATION AT 10-8 AMPS 9.1 Date Time 9.2 Boron Concentration RCS ppm PZR ppm 9.3 Control Bank Position 9.3.1 Actual Position Bank C steps Bank D steps 9.3.2 Minimum Position (8.1) Bank C steps 9.3.3 Maximum Position (8.8.2) Bank D steps Completed By: Date Time Reviewed By: Date Time OS/CRS Salem Common Page 17 of 18 Rev. 0

SC.RE-RA.ZZ-0001 (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

Jyame Sd-'e'. (Print) atur 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

INTEGRAL ROD WORTH (pem) 105 125 115-5 --

I I , ,

133 - - - - - - - - - - - - -- 5

""143 - - I / 15 153-- 25 163d5;/ I..-*---

35 a173 45 183 55 203--------------- - - - - -- ---- 75 o

213---------------- - S - - - - - - - - 85 22 10

- -- 115

w

- - - -- - - - - - - -- 128. '

5 - - -------- - - - - - - - - -- 133 S1 5-------------------1 -

25 153I 35 - - - --- -- - - - - - - -163 W 4 - - - - - - - - - - - 173 55 - - - - 183 65 ------ - - - - - --- - - - --- 193 o 75 -. or -0 203 85 10 213

95. 1: 223 105 -* - - 225 115 [,Im, .

125 000000

",135- ----- : r r--I---r-S~~~145. :",

165 *7. It_' , ,,

175 *. iN 185 e'T ,;

195 205 I, -

,* 215

225tII

(1 ( (

FIGURE 2 S2.RE-RA.ZZ-0012(Q)

SALEM UNIT 2 CYCLE 13 POWER DEFECT VERSUS REACTOR POWER 2600.0 2400.0 2200.0 2000.0 1800.0 S1600.0 1400.0 "1200.0 1000.0 800.0 600.0 400.0 200.0 0.0 0 10 20 30 40 50 60 70 80 90 100 REACTOR POWER (%RTP)

SaleiL Pagt. 43 .:v. 5)f 57

C FIGURE 6 S2.RE-RA.ZZ-0012(Q)

SALEM UNIT 2 CYCLE 13 EQUIBRIUM XENON WORTH vs. PERCENT POWER FOLLOWING PLANT STARTUP AT BOL 2800 2600 2400

.2200 2000 pr 1800 1600 z 1400 0

Si 1200

.1000 800 600 Kr 400 200 0 - *- S- * - i - - S- S S S i S S S S S S S - S S h i S S h S S 0 10 20 30 40 50 60 70 80 90 100 POWER LEVEL (% RTP)

V.

,*(

Salem 2 Page 14 of 43 Rev. 57

( ("

FIGURE 8B S2.R E-RA.ZZ-0012(Q)

SALEM UNIT 2 CYCLE 13 XENON WORTH vs. TIME AFTER TRIP FROM EQULIBRIUM CONDITIONS FOR 25 %, 50 %, 75 % AND 100 % POWER AT MOL 4500 -100 %INITIAL EQUILIBRIUM POWER

-00 % INITIAL EQUILIBRIUM POWER 4000 - -" 75 % INITIAL EQUILIBRIUM POWER

- "- ----- -- - -.---- 50% INITIAL EQUILIBRIUM POWER f1 ,.- .. "--" 25 %INITIAL EQUILIBRIUM POWER 3500 3000 0.

\ %JI j2500 2 2000

-- I '

0 2

w x "-, \ "- --- --

1500

.\4 1000 "500 Shft

.ran._ - L 0

0 10 20 30 410 50 610 70 80 90 100 TIME AFTER TRIP (Hours)

Salej *" Page Iq of 43 57

(

FIGURE 10B S2.RE-RA.ZZ-0012(Q)

SALEM UNIT 2 CYCLE 13 SAMARIUM WORTH vs. TIME AFTER TRIP FROM EQULIBRIUM CONDITIONS FOR 25 %, 50 %, 75 % AND 100 % POWER AT MOL 1250.0 1200.0 1150.0 S000 E

0.

1100.0 0

E 1050.0

([

-100 % NITIALEQUILIBRIUM POWER 1000.0 7- -- 75 %INITIAL EQUILIBRIUM POWER_

50%INITIALEQUILIBRIUM POWER 950.0

".2-- 25 % INITIAL EQUILIBRIUM POWER 900.0 0 50 100 150 200 250 300 350 400 450 500 TIME AFTER TRIP (Hours)

ýSalenw Page2O of 43 Rev. 57

(

FIGURE 12 S2.RE-RA.ZZ-0012(Q)

SALEM UNIT 2 CYCLE 13 DIFFERENTIAL BORON WORTH vs. BORON CONCENTRATION CALCULATED AT 547 deg F

-6.0

-6.5

-7.0 0

o-7.5

-8.0

-8.5

' -9.0 0 200 400 600 800 1000 1200 1400 1600 1800 2000 2200 SOLUBLE BORON CONCENTRATION (ppm)

Salet Page of 43 v.57

(

FIGURE 14 S2.RE-RA.ZZ-0012(Q)

SALEM UNIT 2 CYCLE 13 CONTROL BANK ROD INSERTION LIMITS vs. REACTOR POWER FOR BANK "B", BANK "C" AND BANK "D" 220 16.2- 225 -, 69.5,225 i 210 77 ,i""!.

200

- - - - - - - - - - - - 1 0, 7 S1~80 - 0,186I I f . r I 170

0 .0 "- ,I 1 0 1 0 00,, 17 2

160 " '-=BANK B

'!d,* ,* 15--------------- 140 - - - BANKC -;Po E::'130."', ",' I

120, -- ,A,--

x 110 - - - - I*-- - - - - - - - -

.. 1:00 . ,.1OF v0i '

!i90 0

iiii*

"' . 80 .JI I ' * ' ' '

70 . . ,

4"0- - - - -- - - - - '

20 I I I Il I

70 10,- 209,00 50 60 70 80 90 100 S<!,:,REACTOR POWER (%RTP)

S* SaleM Page )f43 v.57

L,

(

FIGURE 30 S2.RE-RA.ZZ-0012(Q)

SALEM UNIT 2 CYCLE 13 100 %, ARO EQUILIBRIUM POISON BORON CONCENTRATION 1800 1600 1400 r- -- B-10 Depleted

- *,, Nominal I

"1200 3

S=

1000 4,

z .800 0

- b --------------

0 600 -,,i- - - - - -

400

%-4 200 0

0 2000 4000 6000 8000 10000 12000 14000 16000 18000 20000 CYCLE BURNUP (MWD/MTU)

SaleWD 2 Page 3§ of 43 Rev. 57

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

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

TASK NUMBER:

NUMBER: 2002 GOLF NRC RO Al Questions ALTERNATE PATH: KIA NUMBER: See Questions IMPORTANCE FACTOR:

APPLICABILITY: RO SRO EO = ROW- STA = SRO =I 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: N/A APPROVAL:

BARGAINING UNIT TRAINING SUPERVISOR OPERATIONS MANAGER REPRESENTATIVE 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: Minutes JPM PERFORMED BY: GRADE: [ISAT ] UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE:___________ DATE:

Nuclear Common Page 1 of 5 Rev. 0

GOLF GROUP NRC EXAMINATION ADMINISTRATIVE SECTION A.1 - KE 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 0.0111 hours 6.613757e-5 weeks 1.522e-5 months 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

RESPONSE

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

GOLF GROUP NRC EXAMINATION ADMINISTRATIVE SECTION A.1 - ICANDIDATE COP 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

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 - "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 0700-19Q0 Unit 1 P0 watch.

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

ANSWER:

Pre-turnover - prior 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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

RESPONSE

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-825Bj

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 10C607. 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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , 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 Page 5 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 Iia (Including OHA / Panels / Lamps)

CONTROL BOARD WALKDOWN

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)

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

4HiP-DJz 167a(Z SH.OP-DD.ZZ-0067(Z)

FORM SH.OP-DD.ZZ-0067-5 LICENSED OPERATOR / SHIFT TECHNICAL ADVISOR / NUCLEAR EQUIPMENT OPERATOR WATCH STANDING DOCUMENTATION I certify that:

has satisfactorily Name Employee #

(] assumed) ([E assumed under direction) and performed the duties of:

El OPERATIONS SUPERINTENDENT [ NUCLEAR CONTROL OPERATOR Q CONTROL ROOM SUPERVISOR Q NUCLEAR EQUIPMENT OPERATOR El SHIFT TECHNICAL ADVISOR on the shift, this date of at the

[3 Hope Creek Generating Station [3 Salem Generating Station Q] Unit 1[l Unit 2 If duties were "assumed under the direction" of a licensed Reactor or Senior Reactor Operator, the followip must also be done (indicate as appropriate):

(1) *A complete tour of the plant? Q YES D1 NO (2) All required shift turnover procedures completed? El YES El NO For NEOs, indicate watch:

HOPE CREEK SALEM El Reactor El Turbine [] Primary E] Secondary

[] Auxiliary Q Yard El Circ/Service Water CONTROL ROOM SUPERVISOR / OPERATIONS SUPERINTENDENT PLEASE FORWARD THIS COMPLETED FORM TO THE OPERATIONS MANAGER'S SECRETARY.

THE SECRETARY WILL FORWARD THIS FORM TO THE OPERATIONS TRAINING MANAGER AT THE NUCLEAR TRAINING CENTER.

At least one reactivation watch shall include a complete tour of the plant. (Not applicable to LSRO.)

Salem/Hope Creek Page 29 of 31 Rev. I

SH.OP-DD.ZZ-0067(Z)

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 on 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 not assigned to a shift crew but are actively performing license functions, should document their 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 in Section 5.6.l.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 0.0111 hours 6.613757e-5 weeks 1.522e-5 months 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 Page 16 of 31 Rev. I

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

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Administrative Section Examination TASK: Clear and tag an MOV using Manual Tagging TASK NUMBER: 1145370104 JPM NUMBER: 2002 GOLF NRC RO A2 ALTERNATE PATH: K/A NUMBER: 2.2.13 IMPORTANCE FACTOR: 3.6 3.8 APPLICABILITY: RO SRO EO = ROW-7 STA = SRO FW]

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 TRAINING SUPERVISOR OPERATIONS MANAGER REPRESENTATIVE 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: Minutes JPM PERFORMED BY: GRADE: 1 SAT R UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Nuclear Common Page I of 8 Rev. 0

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

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Administrative TASK: 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-00 15. Work is to be performed on 2SJ1 valve motor operator only.

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 8 Rev. 0

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE'ATTACHED FOR FIELD USE 20010621 NC-NA-AP.zz-001s(Q0 4.0 PROCESS DESCRIPTION 4.1 The generation, processing, and implementation of the Safety Tagging Program uE the SAP Work Clearance Module (SAP/WCM) as directed by SH.OP-AP.ZZ-0015(Q),

SAP/WCM Tagging Operations.

NOTE Refer to Attachment 1, Safety Tagging Logic Diagram.

4.2 Equipment requiring Safety Tagging is identified based upon work to be performed, equipment operational restrictions, or procedural requirements.

4.3 A WCD is initiated and identifies the required blocking points, tag types, and position of the blocking points.

4.4 The WCD is:

A. Reviewed B. Approved C. Authorized D. Implemented.

4.5 Clearing Agents review and verify the adequacy of the WCD for the work to be performed. Affected Employees prepare for and execute work under the protection of the WCD.

4.6 At various points in work progression, if required by any Clearing Agent and agreed to by the remaining Clearing Agents, components may be partially or temporarily released to reduce tagging boundaries. A temporary release can be cancelled, and the tags reapplied, at the request of any individual. Tags may be swapped to support work activities, or added to expand the tagging boundary. Finally, work scope may be expanded or deleted; all with the concurrence of Clearing Agents working under the protection of the WCD.

4.7 When all work activities assigned to the WCD are confirmed or appropriately dispositioned, and all Clearing Agents authorize the release of the WCD, then the safety tags can be released.

Nuclear Common Page 4 of 11 Rev. 16 I

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

5.8.1 1. IF the WCM becomes unavailable, Prepare for/ THEN perform the following:

Recover from Manual "a Notify all Clearing Agents to reportfto the WCC to manually Tagging sign on all active WCDs under which they are performing (WCCS) work.

"o Establish a Manual Tagging File in the WCC.

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

Tagging requires approval "a Initiate a new Manual Tagging Index, Form 6, for the Manual of the Operations Manager Tagging File, sequentially number new manually created or designee and should be WeDs beginning with the WCD number 'M00l'.

kept to a minimum. "o Refer to the Manual Tagging file AND the last generated Off In an emergency the on Normal Position Reports for configuration control information.

duty OS may authorize "o Perform tagging operations as directed in the appropriate manual tagging required to sections of this procedure.

move the plant to a safer

2. WHEN the WCM becomes available, condition without the approval of the Operations THEN, perform the following:

Manager. o Enter all outstanding transactions into the WCM.

o. Replace the manual created WCDs with electronically generated WCDs.

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

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

i -

5.8.2 o IF the WCM is unavailable, Create Manual Tags THEN hand write blocking tag information on a blank tag (WCC) sticker in the following format:

Unit WCD#

Blocking Point Description Position Tagged For m I._____

Salem/Hope Creek Page 34 of 67 Rev 11

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020626 SH.OP-AP.ZZ-0015(Q) 5.0 PROCEDURE

Reference to (Note) throughout this procedure indicates that detailed instructions and SAP manipulations are available in the SH.WM-DOZZ-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 Attachment 1.

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.ZZ-0015(Q) 5.1.2 1. Review the following:

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

BlockingPoints "o Work to be performed from SAP Orders (Note) and Tag Types "o Notifications (must be converted to a SAP order (Initiator)

IAW NC.WM-AP.ZZ-0001(Q)).

"u Procedure Requirements "o Controlled Documents and Drawings from the TDR or DCRMS (Note) 0 Main Control Room Drawings for any outstanding Drawing Changes Q Uncontrolled Documents and Drawings that have received an independent field verification 13 Historical, Standard, or Template WCDs for system or component to be tagged (Note)

NOTE

2. Perform the following:

Detailed instructions and "o For ESO switching orders, translate switching order designators SAP manipulations are to the corresponding WCM blocking point designators.

available in "o Resolve Technical and Work Scope problems with:

SH.WM-DG.ZZ-001 5, Work Clearance "* Scheduler Management Desk Guide. "* Planner

"* Implementing Shops

"* WCCSs

", 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 Page 10 of 67 Rev 11

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020626 SH.OP-AP.ZZ0015(Q) 5.1.3 1. Perform the following:

Create Tagging Package o Mark-up Drawings and Documents: (Note)

(Initiator)

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

For system outages, identify ordernumbers for components to be worked on the drawings a 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 blockg points

> For ESO WCDs, include the ESO switching order number Detailed instructions and in the WCD header text SAP manipulations are "* Identify required Discipline Reviews for the following available in ((Note), list on Form I if the WCM is unavailable):

SH.WM-DG.ZZ-O01 5, > Logic circuits, control circuits, or complex electrical Work Clearance blocking points less than 480V Management Desk Guide. > 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 a 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 (drawings, 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 I11 of 67 Rev 11

REFERENCE DRAWINGS:

ABBREVIATIONS I I 2A WEST VALVES & MISC. 23OV. VITAL CONTROL CENTER -.-----.----- - OWG. *222483-A-1778 I I SET. - SETTING 28 WEST VALVES & MISC. 23BV. VITAL CONTROL CENTER --------- --- DWG.*222484-A-1779 I I 00z FV - FULL VOLTAGE 2C WEST VALVES & MISC. 230V. VITAL CONTROL CENTER WIRING DIAG....- - DWG.9203712-A-8853 I I NR - NON-REVERSING CONTACTOR PLUG-IN UNITS WIRING DIAGRAM - -.----- ----------- -- DWG.8220802-A-I404 cnz R - REVERSING ONE-LINE DIAGRAM SYMBOL LIST ....------------------

DWG.960I658-B-9555 SS - SINGLE SPEED SELECTION OF TOL HTR. ELEMENTS FOR SAFETY RELATED MOV'S --.-.-.-- CALC. ES-186.

B oc oiT I I 4rC)

TS -TWOSPEED RONT SW- SINGLE WINDING I I

_]_1_214 TW - TWO WINDING SYMBOLS CDC ATTENT--ION: ANY REVISION TO THIS DRAWINGI A ATT--TIOW*"SHALL BE MADE ONLY BY CAEDO DpiD ATION PLAN G GROUND LUG CA/ 0 NO.2 UNIT AUX.BLDG. SALEM NUCLEAR GENERATING STATION N>

0 -1 LEGEND NO. 2 UNIT-AUXILIARY BUILDING

- INDICATES NOOENUMBERS FOR 2C WEST VALVES & MISC. 230V. VITAL CONTR. CTR. ONE-LINE (0 LOAD MANAGEMENT STUDY DIAGRAM MK. NO. 1-2110 ELECTRICAL 103L cz PSEC NUCLEAR, L.L.C. 0 0

a A

GENERAL NOTES C)

DRAWN _ RLEWIS --- CHECKED R.C. HSU SCALE _NONE USE PRINTS OF LATEST REVISION ONLY. 0 DATE 12-08-86 EXAMINED . A..TLMSON TH N ------------- 0 DO NOT SCALE - USE DIMENSIONS ONLY.

AUTH N- -- APPROVED _R_.. STANLEY FOR LIST OF REFERENCE DRAWINGS SEE DRAWING NO THIS DRAWING THIS DRAWING SUPERSEDES 222485-g-855I-IR 222485 A 1779 -47 CD 8

a 9 9

10 10 11 11

C I-_

2SJ3 R. W.S. T. TO S. I. 2C3YBA-C i

PUMP STOP VALVE 2SJ30-MTRY '-DI 3-12 I IN)I 12110-IAY 0n-II,..

2SJ67 - SAFETY INJECTION PUMIP I MINIFLOW TO RWST VALVE 3-012 2SJ67-MTRY 12110-IEY

] C3YBS-C I, 3-____2__

c-.

SPARE XH I I____

12110-1IY I

I-I ._.

C L I 2SJI R. W.S. T. TO CHARGING 2C3YBO-C PUMPS STOP VALVE 3-512 2SJ1-MTRY EN, ID',

12110-2AY 2CS17 - SPRAY ADDITIVE TANK DISCHARGE VALVE 2CS17-MTRY C 2C3YBE-C 3-81 I

I

(.n 12110-2EY I

I-22CS2 - CONTAINMENT SPRAY PUMP DISCHARGE VALVE 22CS2-MTRY C 2C3YBF-C 3-512 12110-2IY 2C*V140 - CHARGING PUMP RECIRC. STOP VALVE 2CV140-MTRY C 2C3YBG-C 3-612 I 4-12110-3AY 1

C 22SJ33 - SAFETY INJECTION SUCTION VALVE 2C3YBH-C I 22SJ33-MTRY 0f 3-12 3-PI.

7 12110-3EY oc---------

2SJ69 - RUST TO RIR PUMPS 2SJ69-MTRY C O' J IO lO60 P94Ul0-d

.S0 L] 99 9N']YJ0 U)%--aUAdOZO ONI)IdOM 60J O13H0VilV 38 isflVk MOW) ONIGNvis~fno

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020921 SH.OP-AP.ZZ-0015(Q)

ATTACHMENT 2 COMPONENT TAGGING RULES (Page 2 of 13)

MOTOR OPERATED "* 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 manual 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 backseated, 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 from 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

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020921 SH.OP-AP.ZZ-0015(Q)

ATTACHMENT 2 COMPONENT TAGGING RULES (Page 13 of 13)

BEZELS AND CONTROL "* Control Room and Remote Shutdown Panel controls shall be ROOM/REMOTE considered remote operators and shall be tagged with the SHUTDOWN PANEL appropriate 'safety tag' (RBT, WBT, YPT, or WCT) whenever CONTROLS (970103114) that control station will remain operational or become operational while the field tags relating to that component are in place.

"* [F 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.

NOTE "* Bezel Stations that are tagged may be removed from the Control Console for the purpose of checking proper indication/bulbs (with A bezel RBT shall not be OS/CRS permission), provided the tagged position is verified used as the sole isolation when the bezel station is reinstalled.

if a personnel or equipment hazard can " Bezel and Control Room/Remote Shutdown Panel Control RBTs exist due to energized may be used as the sole isolation point when establishing a TEST sources. 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 20020921 SH.OP-AP.ZZ-0015(Q)

ATTACHMENT 3 TAGGING RULES (Page 1 of 5)

RED BLOCKING TAG "* A RBT shall be applied to an energy isolation device for the (RBT) protection of personnel or plant equipment.

"* RBT stickers vice tags may be used when the blocking point is a switch/bezel so as to not obstruct the view of other remote switches in the area.

"* OS/CRS/WCCS shall only authorize the manipulation of a blocking point with a RBT affixed in the tagged direction for position verification or in an attempt to limit leakage.

"* In an emergency, the OS can authorize the repositioning of a RBT component if it presents an immediate challenge to the safety of personnel or plant equipment.

> Prior to component operation, all personnel shall be verified clear of affected equipment, and, following component manipulation, all personnel signed on the WCD will be notified.

SPECIAL

Used to allow instructions to be sequenced into a WCD. This INSTRUCTIONS allows clarification or additional guidance in the body of the WCD.

(SPI) SPI(s) do not transfer to the Tagging Release and must be entered into the Full Tagging Release.

INF tags shall not be used as a safety tag to block use of a INFORMATION TAG component or for configuration control.

(INF) e INF tags can be used in the Control Room and in the field to alert the operators that a component is tagged.

IF a WCD will affect remote operation or indication, THEN an INF tag or bezel cover shall be placed on the console device to alert operators of the abnormal condition.

e INF bezel covers not listed on the blocking point page shall be annotated in both the WCD tagging and untagging text to ensure the bezel cover is removed when the WCD is released.

Independent verification for hanging or releasing INFs is not required.

Addition of an INF tag to a WCD is not required to go through a review process and may be added, approved, and issued at any time.

Salem/Hope Creek Page 51 of 67 Rev 11

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020626 SH.OP-AP.ZZ-OOI5(Q)

FORM I WORK CLEARANCE DOCUMENT:.

ESO NUMBERLi EQUILPMENT UNAVAILABLE/Refermnce object: g. /

COMMENTS:

SPECIAL INSTRUCTIONS FOR TAGGING:

INITIATED BY: DATE:

PRE-APPROVED BY:

WCD AUTHORIZED BY: DATE:

(ON-DUTY OS/CRSIWCCS)

SPECIAL INSTRUCTIONS FOR RELEASE:

WCD RELEASE APPROVED BY: DATE:

RELEASED CONFIRMED (IF WCM WAS UNAVAILABLE UPON REQUEST)

Salem/Hope Creek Page 60 of 67 Rev 11

Or or SH.OP-AP .ZZoo05(Q) o FORM 4 TAGGINGIUNTAGGING WORK LIST I.J "-4.

0

[,REQUEST Iz

[0 RELEASE TYPE (circle one) FULL PARTIAL TEMPORARY DISCIPLINE REVIEWS: a AKA

-u-"

0z W LEIdentifier TNUMBER WCM TamPoit eu~i t£"ag Position Curn stisn Desire /T Date/Tm-' Piage O of Verified--

Apply/Relea--'-- ---

SX.C 0

mm~mmm TAGGED BY: DATE/TIME: VERIFIED BY: DATE/TIME:

Salem/Hope Creek Page 63 of 67 Rev 11

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

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE 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)

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, Locates Form 6 in procedure. Give Form 6 and sequentially numbers new Candidate blank Form 6. Enters 'M001' in manually created WCD's beginning with WCD/Manual Number column.

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 Nuclear Common Page 3 of 8 Rev. 0

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

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Administrative TASK: Clear, tag and manually close an MOV STEP COMMENTS

STEP

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 tagging evolutions ......... apply Step 5.3 Step 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 Nuclear Common Page 4 of 8 Rev. 0

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

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE 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)

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),valve haridwheel, and Candidate locates 2SJ1 bezel control need Red Blocking drawing, Examiner Tags applied, will provide a copy for student to mark NOTE: Candidate may elect to use "TRIS" up.

identifier 2CY2AX2A for breaker, this information is in a table on the drawing Nuclear Common Page 5 of 8 Rev. 0

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

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE 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/IU 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 Nuclear Common Page 6 of 8 Rev. 0

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

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE 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

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

Terminating Cue: Review the completed Form 4 and then state "This JPM is complete".

Nuclear Common Page 7 of 8 Rev. 0

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

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.

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

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

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Administrative Section Examination TASK: Perform control room actions for a fuel handling incident in the Fuel Handling Building (FHB)

TASK NUMBER: 1140170401 JPM NUMBER: 2002 GOLF NRC RO A3 ALTERNATE PATH: [ KIA NUMBER: 2.3.10 IMPORTANCE FACTOR: 2.9 3.3 APPLICABILITY: RO SRO EO Z RO F-- STA

SROfl 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:

BARGAINING UNIT TRAINING SUPERVISOR OPERATIONS MANAGER REPRESENTATIVE 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: 15 Minutes ACTUAL TIME CRITICAL COMPLETION: N/A JPM PERFORMED BY: GRADE: rISAT - UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Nuclear Common Page 1 of 7 Rev. 0

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

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Fuel Handling Incidents (APE 036)

TASK: 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 Page 2 of 7 Rev. 0

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

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Fuel Handling (034)

TASK: Perform Control Room actions for a fuel handlina incident in the Fuel Handlina Buildina IFHRI

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 Page 3 of 7 Rev. 0

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

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Fuel Handling (034)

TASK: Perform Control Room actions for a fuel handling incident in the Fuel Handling Building (FHB)

- STEP STEP COMMENTS NO. (*Denotes a Critical Step) STANDARD EVAL (Required for

(#Denotes a Sequential Step) STANDARD 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

HEPA 22 PLUS CHAR and SEQUENCE COMPLETE lights SEQUENCE COMPLETE lights illuminate, illuminated.

"* HEPA 21 ONLY and SEQUENCE e 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 Page 4 of 7 Rev. 0

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

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Fuel Handling (034)

TASK: Perform Control Room actions for a fuel handling incident in the 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 CNMT}*.

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 NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Fuel Handling (034)

TASK: Perform Control Room actions for a fuel handling incident in the Fuel Handling Building (FHB)

STEP STEP COMMENTS

NO. (*Denotes a Critical Step) STANDARD EVAL (Required for

(#Denotes a Sequential Step) S/U UNSAT evaluation)

3.15 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.

e 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 Page 6 of 7 Rev. 0

NC.TQ-WB.ZZ-031 0(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 <1R/hr and no one has been injured. Implement S2.OP AB.FUEL-0001, Fuel Handling Incident.

Nuclear Common Page 7 of 7

63/4'vec /Z /V SALEM/OPERATIONS Page 1 of 1 S2.OP-AB.FUEL-0001(Q) - REV. 3 FUEL HANDLING INCIDENT REVISION

SUMMARY

Biennial Review performed Yes No V_

The following changes to this procedure contain only editorial enhancements as described in NC.NA-AP.ZZ-0001(Q):

Deleted the following Radiation Monitors LAW DCP 80004831, Deletion of RMS Channels 2R24A & B, 2R25, 2R28, 2R29, 2R30, and 2R33 (CD519, dated 08/23/00) from the TBD: [RR2241]

2R28, Spent Fuel Pool Filter 2R29, Spent Fuel Pool Skimmer Filter

Upgraded to latest administrative standards (revision bars not used).

Changed SC.OP-DL.ZZ-0001(Q), Control Room Operator/Supervisor Logs to SC.OP-AP.ZZ-0004(Q), Cyclic Data Monitoring Program.

PSE&G CON TROL

'-' ' * .:_L

. 4-.

IMPLEMENTATION REQUIREMENTS Effective Date q9/13 Lcc

None i41 APPROVED: ,/, /00 perations Manager Date q j~ o"'

S2 .OP-AB.FUEL-0001(Q)

FUEL HANDLING INCIDENT 1.0 ENTRY CONDITIONS DATE: TIME:

1.1 Any incident involving nuclear fuel with indication of damage to fuel assembly or a radiological release.

2.0 IMMEDIATE ACTIONS 2.1 None 3.0 SUBSEQUENT ACTIONS 3.1 INITIATE Attachment 1, Continuous Action Summary.

3.2 NOTIFY personnel at the scene of the incident to:

A. STOP all fuel transfers in progress.

B. EVACUATE all non-essential personnel from the scene.

3.3 Has the incident occurred in the Fuel Handling Building?

YES NO -> GO TO Step 3.8 Time V

NOTE Emergency actions are dependent upon the location of the fuel assembly. The quickest path should be taken to place the fuel assembly in a safe condition.

3.4 NOTIFY personnel in the Fuel Handling Building to place any fuel assembly being handled into the emergency rack X-3, or designated location, whichever takes less time.

3.5 PRESS FUEL HANDLING BUILDING VENTILATION, EXH FLTR TRAINS, HEPA 22 PLUS CHAR pushbutton.

Salem2 Page 1 of 7 Rev. 3

s2.OP-AB.FUEL-0001(Q) 3.6 ENSURE the following:

_ A. All available Fuel Handling Building Exhaust Fans are running.

_ B. HEPA 22 PLUS CHAR and SEQUENCE COMPLETE lights illuminate.

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

_ D. RECORD Time I/S in SC.OP-AP.ZZ-0004(Q), Cyclic Data Monitoring Program.

3.7 GO TO Step 3.12 Time 3.8 Has the incident occurred in Containment?

NO YES -> GO TO Step 3.10 Time V

3.9 RETURN to Step 3.1 for symptom rediagnosis or as directed by the CRS.

NOTE Emergency actions are dependent upon the location of the fuel assembly. The quickest path should be taken to place the fuel assembly in a safe condition.

3.10 NOTIFY personnel at the scene of the incident to perform one of the following:

A. IF the mast tube is indexed over the upender, THEN INSERT the fuel assembly in the upender AND LOWER the upender to the horizontal position.

B. IF the mast tube is NOT indexed over the upender, THEN PLACE the fuel assembly into the core in its designated location, OR the emergency location P-10 whichever takes less time.

C. IF the P-10 is NOT available (i.e. refueling is at the core peripheral area),

THEN PLACE the fuel assembly in the upender and lower the upender to the horizontal position.

Salem2 Page 2 of 7 Rev. 3

S2.OP-AB.Ft L-0001(Q) 3.11 ISOLATE Containment as follows:

A. INITIATE S2.OP-AB.CONT-0001(Q), Containment Closure.

B. ISOLATE Containment Ventilation by closing the following Valves:

2VC1, CONTAINMENT PURGE, SUPPLY VALVE

2VC2, CONTAINMENT PURGE, SUPPLY VALVE

2VC3, CONTAINMENT PURGE, EXHAUST VALVE

2VC4, CONTAINMENT PURGE, EXHAUST VALVE

2VC5, PRESSURE & VACUUM RELIEF ISOL VLV

2VC6, PRESSURE & VACUUM RELIEF ISOL VLV 3.12 NOTIFY Radiation Protection of the following:

Location of incident

Details of incident

Affected personnel, if any

SURVEY the area to determine radiological conditions

+ SAMPLE the area for airborne activity and contamination 3.13 IF fuel transfer cart is in the Fuel Handling Building or Fuel Transfer Canal, THEN RETURN the fuel transfer cart to the Containment.

3.14 IF the fuel transfer canal gate valve is open, THEN CLOSE the valve to isolate Spent Fuel Pool from Containment.

3.15 NOTIFY all personnel at the scene of the incident to perform the following:

EVACUATE the affected area.

CLOSE all doors upon exiting.

REPORT to the Control Point.

3.16 NOTIFY Reactor Engineering of the incident and request assistance.

Salem 2 Page 3 of 7 Revi 3

S2.OP-AB.FUEL-0001(Q) 3.17 NOTIFY the OS/CRS to refer to the Event Classification Guide and Technical Specifications.

3.18 When the cause of the incident is corrected and Radiation Protection concurs:

RETURN Fuel Handling Building ventilation to normal IAW S2.OP-SO.FHV-0001(Q), Fuel Handling Building Ventilation.

RETURN Containment Ventilation Systems to normal IAW S2.OP-SO.CBV-0001(Q), Containment Ventilation Operation.

RESTORE access to Containment.

4.0 COMPLETION AND REVIEW 4.1 CIRCLE Entry Condition number in Section 1.0, OR EXPLAIN Entry Condition in Comments Section of Attachment 2.

4.2 COMPLETE Attachment 2, Sections 1.0 and 2.0, AND FORWARD this procedure to OS/CRS for review and approval.

4.3 OS/CRS PERFORM:

__A. REVIEW this procedure with Attachments 1 and 2 for completeness and accuracy.

B. COMPLETE Attachment 2, Section 2, 3.0.

C. FORWARD completed procedure to Operations Staff.

END OF PROCEDURE S,em2 Page 4 of 7 Rev. 3

S2.OP-AB.FUEL-0001(Q)

ATTACHMENT 1 (Page 1 of 1)

CONTINUOUS ACTION

SUMMARY

1.0 IF AT ANY TIME radiation levels in the Fuel Handling Building or Containment reach or exceed 1 R/hr, THEN EVACUATE ALL personnel from the affected area.

2.0 IF AT ANY TIME Radiation Protection airborne sample results indicate Iodine activity in Containment, THEN OPERATE Iodine Removal Units as follows:

NOTE IRUs should be run only if iodine is present in Containment or when requested by Radiation Protection.

A. PRESS Iodine Removal Unit 21 OR 22 START bezel.

B. ENSURE SEQUENCE COMPLETE bezel illuminated for Unit(s) started.

C. ENSURE AIR FLOW LO bezel alarms NOT illuminated.

D. RECORD Charcoal Filter Time I/S in SC.OP-AP.ZZ-0004(Q),

Cyclic Data Monitoring Program.

Salem2 Page 5 of 7 Rev. 3

s2.OP-AB.FuEL-OO1 (Q)

ATTACHMENT 2 (Page 1 of 2)

COMPLETION SIGN-OFF SHEET

1.0 COMMENTS

(Include procedure deficiencies and corrective actions. Attach additional pages as necessary.)

Salem2 Page 6 of 7 Rev. 3

S2OP-AB.FuEL-ooo1(Q)

ATTACHMENT 2 (Page 2 of 2)

COMPLETION SIGN-OFF SHEET COMMENTS: (continued)

2.0 SIGNATURES

Print Initials Signature Date 3.0 OS/CRS FINAL REVIEW AND APPROVAL:

This procedure with Attachments 1 and 2 is reviewed for completeness and accuracy. Entry conditions and all deficiencies, including corrective actions, are clearly recorded in COMMENTS Section above.

Signature: Date:

OS/CRS Salem2 Page 7 of 7 Rev. 3

S2.OP-AB. FUEL-0001(Q)

FUEL HANDLING INCIDENT TECHNICAL BASES DOCUMENT

1.0 REFERENCES

1.1 Technical Documents A. Salem Generating Station Updated Final Safety Analysis Report:

1. Section 9.1, Fuel Storage and Handling

2. Section 11, Radioactive Waste Management

3. Section 15.4, Condition IV Faults, Fuel Handling Accident B. Salem Generating Station Technical Specifications Unit 2:

1. Table 3.3-6, Radiation Monitoring Instrumentation

2. Table 3.6-1, Containment Isolation Valves

3. 3.6.3, Containment Isolation Valves

4. 3.7.7, Auxiliary Building Exhaust Air Filtration System

5. 3.9.9, Containment Purge and Pressure-Vacuum Relief Isolation System

6. 3.9.12, Fuel Handling Area Ventilation System C. Configuration Baseline Documentation:

1. DE-CB.FHV-0021(Q), Fuel Handling Area Ventilation System, Section 7, Accident Analysis D. Technical/Engineering Letters:

1. S-1-N300-MSE-0012, Accident Analysis, Fuel Handling Accident No. 1 Unit, Salem Nuclear Generating Station 1.2 Procedures A. S2.OP-SO.CBV-0001(Q), Containment Ventilation Operation B. S2.OP-SO.ABV-0001(Q), Auxiliary Building Ventilation Operation C. S2.OP-SO.FHV-0001(Q), Fuel Handling Building Ventilation D. S2.OP-ST.CAN-0006(Q), Refueling Operations - Containment Isolation E. S2.OP-ST.FHV-0001(Q), Refueling Operations - Fuel Handling Building Ventilation F. S2.OP-AB.RAD-0001(Q), Abnormal Radiation G. S2.OP-AB.CONT-0001(Q), Containment Closure H. SC.OP-AP.ZZ-0004(Q), Cyclic Data Monitoring Program I. SC.RE-FR.ZZ-0010(Q), Unanticipated Water Level Decrease Procedure Salem 2 Page 1of 4 Rev. 3

S2.OP-AB.FUEL-0001(Q) 1.3 Drawings A. 203566, No. 1 & 2 Units Fuel Handling Area Vent. No. 11, 12, 21 & 22 Exhaust Filter Units B. 205338, Unit No. 2 Containment Ventilation C. 205322, Unit No. 2 Diesel Area and Fuel Handling Building D. 239989, No. 1 & 2 Units Fuel Handling Area Vent. No. 1 & 2 Supply Units &

No. 11, 21, 12 & 22 Exhaust Filter Units 1.4 Conformance Documents - None 1.5 Industry Concerns A. INPO SER 82-43, Fractured Fuel Assembly Guide Tubes B. INPO SER 86-21, Dropped Fuel Assembly at a PWR C. NRC INFO 83-29, Fuel Binding Caused By Fuel Rack Deformation D. NRC INFO 85-12, Recent Fuel Handling Events E. NRC INFO 86-58, Dropped Fuel Assembly at Haddam Neck Plant 1.6 Other A. DCP 2EC-3559, Fuel Handling Area Ventilation Exhaust Fan Interlock with Radiation Monitors.

B. DCP 80004831, Deletion of RMS Channels 2R24A & B, 2R25, 2R28, 2R29, 2R30, and 2R33 Salem 2 Page 2 of 4 Rev. 3

s 2 .op-A.FUE-oooi (Q) 2.0 DISCUSSION This procedure provides the instructions to follow during a Fuel Handling Incident. It is the intent of this discussion to provide the reasoning behind the logic and flowpath of the procedure. It is not intended to provide additional direction to the procedure.

2.1 Entry Conditions - Entry conditions are based upon Refueling personnel recognizing a Fuel Handling Incident and reporting same to the Control Room. The symptoms available to personnel involved are as follows:

Actual observation of a Fuel Handling Incident

Gas bubbles or discoloration of water in the vicinity of a fuel assembly

+ Increasing activity or alarm on Radiation Monitors:

2R1lA, Containment Sampling Particulate

2R12A, Containment Sampling Noble Gas

2R12B, Containment Sampling Iodine

"* 2R2, Containment - 130' elevation

2R5, Fuel Handling Building

2R9, Fuel Storage Area

2R32A, Fuel Handling Crane

2R44B, Stairway to Reactor Sump - 96' elevation 2.2 Immediate Actions - None Salem 2 Page 3 of 4 Rev. 3

S2.OP-AB.FUEL-0001(Q) 2.3 Subsequent Actions - When it is determined that a Fuel Handling Incident has occurred, all fuel transfers in progress are stopped. It is then determined where the incident has occurred and fuel in transit is-placed in the nearest available safe location.

In the event the incident occurs in the Fuel Handling Building, any assembly in transit is placed in the emergency rack X-3, or designated location, whichever takes less time.

If the incident occurs in the Containment, the refueling team is given the option of placing any fuel assembly in transit: in the upender when the mast tube is indexed over it, in the core in its designated location, or P-10 the emergency location whichever takes less time. When the assembly is placed in the Upender, the frame is lowered to the horizontal position.

Containment Closure is established, if applicable, and the affected area ventilation system is aligned to provide protection of personnel and the general public from possible airborne activity. Radiation Protection is notified to determine the Radiological conditions resulting from the incident.

Steps 3.13 and 3.14 then direct isolation of the Spent Fuel Pool from the Containment by first clearing the Fuel Transfer Tube of the Fuel Transfer Cart, and then closing the Fuel Transfer Tube Gate Valve.

Once all required fuel local protective actions are completed, the affected area is evacuated in Step 3.15. Reactor Engineering is contacted for assistance in determining further actions to be taken for any actual fuel damage. The Event Classification Guide is referenced to ensure compliance with the Emergency Plan and to satisfy any reporting requirements. Applicable Technical Specifications are referenced to ensure License compliance.

High Iodine activity levels in the Containment are reduced using the installed Iodine Removal Units. Once the cause of the incident is determined and required restoration actions performed, the procedure is exited and normal operations resumed.

END OF DOCUMENT Salem 2 Page 4 of 4 Rev. 3

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

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

TASK NUMBER:

JPM NUMBER: 2002 GOLF NRC RO A4 Questions ALTERNATE PATH: K/A NUMBER: See Questions IMPORTANCE FACTOR:

APPLICABILITY: RO SRO so =--- ROrF- STA = SRO r--

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: N/A APPROVAL:

BARGAINING UNIT TRAINING SUPERVISOR OPERATIONS MANAGER REPRESENTATIVE 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: Minutes JPM PERFORMED BY: GRADE: [ISAT D UNSAT REASON. IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE:___________ DATE:

Nuclear Common Page 1 of 5 Rev. 0

GOLF GROUP NRC EXAMINATION ADMINISTRATIVE SECTION A.4 - ICANDIDATE COPY 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 -FKE 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.

RESPONSE

REFERENCE:

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

GOLF GROUP NRC EXAMINATION ADMINISTRATIVE SECTION A.4 - ICANDIDATE COP 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

GOLF GROUP NRC EXAMINATION ADMINISTRATIVE SECTION A.4 -FKE 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.

RESPONSE

REFERENCE:

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

Nuclear Common Page 3 of 5

(,tu&d T6ZPZ,z ECG ATT 8 Pg. 1 of 9 ATTACHMENT 8 SECONDARY COMMUNICATOR LOG Table of Contents Pages 1-2 3-4 Notifications & Data Collection/Transmission Incoming Calls (BNE, DEMA, OEM, AAAG, etc.) i'

((-)7 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/EOF2

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 hitLher emereencv:

( ) a. CALLOUT an additional SRO and have him/her report to the OSC.

Name: Time:

CM2

b. ACTIVATE ERDS within 60 minutes from the Affected Unit's SPDS terminal:

I) PRESS <UNIT MASTER MENLI> key.

2) PRESS <ERI)S> key.

3) FO1l.LOW screen prompts.

CM2 SGS Rev.07

ECG ATT 8 Pg. 2 of 9 Initials A. NOTIFICATIONS (cont'd)

4. OBTAIN a copy of the ICMF and FAX the ICMF to Group A.

CM2/TSC2/EOF2

5. COMPLETE a Station Status Checklist (SSCL) Form, Pg. 7 or Common Site UNUSUAL EVENT Station Status Checklist (SSCL) Form, Pg. 9;

( ) a. OBTAIN OS (TSS/SSM) assistance, as needed for SSCL Pg. 1.

( ) b. OBTAIN SRPT (RAC/RSM) assistance, as needed for SSCL Pg.2. (N/A for Common Site)

( ) c. FAX to Group B.

( ) d. IF fax transmission of the SSCL is incomplete, THEN CONTACT the State Agencies listed below, READ the data. AND DOCUMENT on SSCL. Pg. 2.

DEMA Delaware Emergency Management Agency 302-659-2290 BNE NJ Bureau of Nuclear Engineering 609-984-7700 CM2/TSC2/EOF2

6. OBTAIN completed NRC Data Sheet from the CM-I. and FAX form to Group B. CM2/TSC2/EOF2

7. REPEAT Step 5 approximately every half hour OR IMMEDIATELY for significant changes in Station status. until either Turnover or relief.

CM2/TSC2!EOF2

8. TURNOVER responsibility for ofisite notifications and offsite data updates (SSCLs) to the oncoming facility (TSC or EOF):

a. GIVE names and phone numbers of contacts already made with any Offsite Agencies.

) b. GIVE time for next SSCL.

CM2/TSC2

9. IF available for other duties AND TSC turnover is complete, THEN obtain headset. MAN the Ops Data line and CONTACT the TSC ops advisor and establish an open line of communication from the control room to the TSC.

CM-2 B. DATA COLLECTION/TRANSMISSION I. WHEN in an ALERT or higher emergenc%

OR AFTER significant changes in plant status THEN COMPLFTI- the Major Equipment and Electrical Status (MEES) Form.

( ) a. OBTAIN l.icensed Operator re' ie%

b. GIVE a cop. to the ()S(" Coordinator

c. FAX to (Group C.

CM2 SGS Rev.07

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 every 15 minutes.

(TSS may modify the frequency or data list as appropriate)

( ) a. OBTAIN Licensed Operator review.

( ) b. FAX to GroupC.

CM2

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

( ) a. OBTAIN OSB Data from SPDS "Unit Master Menu."

( ) b. IF SPDS is Out of Service, THEN REQUEST CM2 to perform step B.2, above. (data set and frequency of updates may be revised by the TSS based on event circumstances)

( ) 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 OS (TSS/SSM).

CM2/TSC2/EOF2 C. INCOMING CALLS STATE OFFICIALS I1. IF Notifications authority has transferred.

THEN DIRECT the caller to contact the TSC (or EOF if activated).

CM2/TSC2

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

DEMA - Delaware Emergency Management Agency AAAG - Delaware Accident Assessment Advisory Group BNE - NJ Bureau of Nuclear Engineering DEP - NJ Department of Environmental Protection OEM - NJ Office of Emergency Management PERFORM the following:

a. OBTAIN and RECORD:

Agency Caller's Name Phone #

b. READ the latest EC approved SSCL.

SGS Rev.07

ECG ATT 8 Pg. 4 of 9 Initials C. INCOMING CALLS (cont'd)

STATE OFFICIALS

( ) c. IF caller is NJ-BNE, DEMA, or AAAG, THEN also READ the approved NRC Data Sheet Event Description.

CM2,/SC2/EOF2 NEWS MEDIA CAUTION Communicators are NOT authorized to release any information to the News Media.

3. WHEN contacted by any News Media representative, READ the appropriate message below:

( ) a. IF the ENC is not activated (Unusual Event), say; "You are requested to contact the Nuclear Communications Office at the following number: 856-339-1186."

( ) b. IF the ENC is activated (ALERT or higher), say; "You are requested to contact the Media Information Operator at any of the following numbers: 856-273-0188, -0282, -0479, or 0586."

C M2/TSC2!EOF2 NRC OPERATIONS CENTER

4. WHEN directed by the NRC to TERMINATE ERDS transmission, THEN GO TO any SPDS terminal of the affected Unit AND PROCEED as follows:

a. PRESS <UNIT MASTER MENU> key.

b. PRESS <ERDS> key.

c. FOLLOW screen prompts.

d. WHEN completed. NOTIFY the OS.

CM2 SGS Rev.07

ECG MEES ATT 8 Pg. 5 of 9 SALEM UNIT DATE:

UPDATE TIME:

MAJOR EQUIPMENT AND ELECTRICAL STATUS P -- ------

ECCS ELECT. CONTAINMENT ELECT.

SYSTEMS FEED Y/N CONTROL FEED Y/N NOTE: Y = IN SERVICE CHARGING I B9D CONT. SPRAY 1 A2D N = OUT OF SERVICE PUMPS 2 C9D PUMPS 2 C2D (CIRCLE ANY UNAVAILABLE EQUIPMENT) 3 A7X CFCU HI ILOW SAFETY INJ 2 A5D I A3X A2X A4X PUMPS 2 C5D B3X B2X B4X I-

___________________________________________________ I -

RHR I A7D 3 C3X C2X C4X

- i-COOLING ELECT. PUMPS 2 B7D 4 B7X B6X B8X SYSTEMS FEED Y/N I -

___________________________________________________ i -

ELECTRICAL STATUS 5 C7X C6X C8X Y/N ________________I - I - I - U -

AUX FD I AID ELECT.

PUMPS 2 BID OFFSITE AC POWER AVAILABLE FEED Y/N

+--------------- -

3 STM. EMERGENCY DIESELS KUN LUADJ-D IODINE I J7X SERVICE I I-I 3D EDG A 1 r REMOVAL E7X F II________________________________________________

WATER 8D B HC I Ai5X PUMPS 3 B3D C RECOM 2 BI5X 4 B8D #3 GAS TURBINE a MISC. EQUIPMENT ELEC DISTRIBUTION I -

___________________________________________________ I Y/N 5 3D ELEC DISTRIBUTION

.4-6 8D AVAILABLE? Y/N FIRE PUMPS I i -

____________________________________________ I -

(DIESEL) 2 COMP. I AIOD VITAL BUS A

________________________________________________ U ___________

I __________________

COOLING 2 BIOD B ELECT.

PUMPS 3 CIOD C STATION AIR COMP. FEED Y/N REACTOR I H4D GROUP BUS E I IH6D COOLANT 2 E4D F 2 2GID PUMPS 3 F4D G 3 IGID 4 G4D H EMERGENCY AIR ELECT.

CONDENSATE 1 HID COMP. FEED Y/N PUMPS 2 EID I ICI4X 3 FID 2 2C14X U1/U2 COMMENTS:

CIRC ]A 2AD/2AD WATER IB 7BD/7BD PUMPS 2A 3AD/3AD 2B 6BD/6BD 3A 4AD/4AD 3B 5BD/5BD

_______________________________________i I______

LICENSED OPERATOR REVIEW:

INITIALS CcSG Rev.07

( Operational Sty' -s Board - Salem (

UPDATE:

UNIT #llZ TIME DATE I. EMERGENCY CORE COOLING SYSTEM IV. C.V.C.S Cent. Charg. Pump Flow (BIT flow) GPM Letdown flow SIP flow # 1 GPM Charging flow K+iGPM GPM SlP flow # 2 RHR P flow # 1 GPM V. SECONDARY COOLANT SYSTEM RHR P flow # 2 GPM NO. 1 SG level % (NR or WR)

RWST LEVEL FT NO. 2 SG level % (NR or WR)

II.CONTAINMENT NO. 3 SG level % (NR or WR)

Cont Pressure PSIG NO. 4 SG level % (NR or WR)

Cont. Temperature (AVG) F NO. 1 SG pressure PSIG Cont. H2 Concen. NO. 2 SG pressure PSIG Cont Sump level NO. 3 SG pressure PSIG Cont Rad (hi range) R44A R/hr NO. _4 SG pressure PSIG Cont. Rad (hi range) R44B R/hr NO. 1 SG feedflow % or LBS/HR II!. REACTOR COOLANT SYSTEM NO. 2 SG feedflow % or LBS/HR

of RCPs Running NO. 3 SG feedflow % or LBS/HR RVLIS (full range) NO. 4 SG feedflow % or LBS/HR Core Exit Thermocouple (hottest) F AFST level

of Thermocouples > 1200 OF VI. MISC. TANKS LEVEL Tc Loop 1 F Waste Hold-Up Tank #_1 Tc Loop 2 F Waste Hold-Up Tank #_2 Tc Loop 3 F Waste Monitor HUT Tc Loop -4 F VII. SSCL INFORMATION NO

Tave (Autioneered) *Ifno RCPs running. Tave on F Offsite power available?

PZR/RCS Pressure the Control Console is invalid. PSIG Two or more diesels available?

PZR Level (hot) Did ECCS actuate?

Th Loop 1 F Is the containment barrier failed?

Th Loop 2 F SIGNIFICANT PLANT EVENTS Th Loop 3 F VIll.

Th Loop 4 F Reactor Power/Neutron flux %/amps/CPS)

Subcooling Margin F Licensed Operator Review Initials ECG Paqe 6 of 9 SGS Rev. 07

ECG I SSCL STATION STATUS CHECKLIST ATT 8 (Pg. 1 of 2) Pg. 7 of 9 Operational Information SALEM GENERATING STATION Unit No.__ Message Date Time Transmitted By: Name Position (CR/TSC/EOF)

1. Date and Time Event Declared: Date Time (24 hr clock)

2. Event Classification: 0l Unusual Event El Site Area Emergency 0l Alert 0 General Emergency

3. Cause of Event: Primary Initiating Condition used for declaration EAL #(s)

Description of the event

4. Status of Reactor: El Tripped/Time _________________

4. Status of Reactor: 0] Tripped/Time o At Power El Startup El Hot Standby El Hot Shutdown El Cold Shutdown El Refuel

5. RZR/RCS Pressure psig Core Exit TC OF

6. Is offsite power available? 0l YES O NO

7. Are two or more diesel generators available? D YES O NO

8. Did any Emergency Core Cooling Systems actuate'? D YES O NO

9. Is the Containment barrier failed? (Loss per EAL section 3.3) 0 YES D NO

10. Other pertinent information Approved:

EC or TSS or SSM SGS Rev. 07

STATION STATUS CHECKLIST (PAGE 2 OF 2) ECG RADIOLOGICAL INFORMATION ATT 8 Pg. 8 of 9 SALEM GENERATING STATION UNIT NUMBER: CALCULATION TIME: DATE:

1. GASEOUS RELEASE>TECH SPEC (T/S) LIMITS:

(T/S LIMITS: 2.42 E+05 gCi/sec NG or 2.1E+01 gCi/sec IODINE)

YES: [ ] RELEASE START TIME: DATE:

NO:[

A. RELEASE TERMINATED: YES [ ]NO [ ] N/A[

B. ANTICIPATED OR KNOWN DURATION OF RELEASE: HOURS C. TYPE OF RELEASE: GROUND[ ] ELEVATED: [ ]N/A [ )

D. ADJUSTED WIND SPEED: (mph) _ (m/sec) WIND DIR (deg from) __

E. STABILITY CLASS: (A-G) DELTA T: __ (deg C)

F. VENT PATH OF RELEASE: R41 [ ] R45 [ I R44[ ] R46 G. NG RELEASE RATE: R41 R45_ R44 R46 (pCi/sec)

H. 1-131 RELEASE RATE: R41 R45 R44 R46 DEFAULT (pCi/sec) (circle if default)

I. TOTAL RELEASE RATE NOBLE GAS: .(pCi/sec)

J. TOTAL RELEASE RATE IODINE-131:" (pCi/sec)

2. PROJECTED OFFSITE DOSE RATE CALCULATIONS:

TEDE DISTANCE XU/Q TEDE DOSE THYROID THYROID TIME FOR PLUME FROM VENT RATE (4 DAY) CDE RATE CDE DOSE TO TRAVEL (IN MILES) (I/M2) (MREM,:HR) (MREM) (MREM/HR) (MREM) (MIN)

MEA 0.79 2.00 LPZ 5.00 EPZ 10.00

3. OTHER PERTINENT INFORMATION:

4. UPDATE TO STATES (IF VIRBANI.Y TRASMITTEI)I NAME TIME INITALS STATE OF NIV9, JLRSI 'Y STATE OF I)ILLAW'ARI.

AGENCY APPROVED:

EC or RAC or RSM SGS Rev. 07

ECG ATT 8 Pg. 9 of 9 Common Site Unusual Event STATION STATUS CHECKLIST Operational Information Message Date Time Transmitted by: Name Position

1. Date and Time Event Declared: Date Time:

2. Cause of event: Primary Initiating Condition used for declaration EAL#

Description of the event:

33FT. LEVEL WIND DIRECTION (From): WIND SPEED (From MET Computer) (DEGREES) (MPH)

3. Status of Mode: (Power. Startup. Rx Pressure Hottest Core Exit Rx Water the Reactors Hot Standby. Hot S/D. TC / Rx Temp Level Cold S/D. Refuel)

Salem 1 psig 'F covered Salem 2 psig 'F covered Hlope Creek psig OF in.

Salem I Salem 2 Hope Creek YES NO YES NO YES NO

4. Is offsite power available?

5. Are two or more diesel generators operable?

6. Did any Emergency Core Cooling Systems actuate?

7. Is any Containment Barrier failed? (Loss per EAL section 3.3)

8. Radiological release (> Tech Spec Limit) in progress X X X

9. Other pertinent information EC Initials (Approval to Transmit ICMF)

SGS Rev. 07

Nb.trQ-WB.ZZ-031 0(Z)

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Administrative TASK: Evaluate a shift staffing situation and take corrective action lAW administrative procedures TASK NUMBER: 1210020302 JPM NUMBER: GOLF NRC - SRO A.1 ALTERNATE PATH: LJ K/A NUMBER: 2.1.4 IMPORTANCE FACTOR: 2.3 3.4 APPLICABILITY: RO SRO EO = RO - STA - SRO W 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: ISI/A APPROVAL:

BARGAINING UNIT TRAINING SUPERVISOR OPERATIONS MANAGER REPRESENTATIVE 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: N/A JPM PERFORMED BY: GRADE: D SAT D- UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Nuclear Common Rev. 0 Page 1 of 5

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 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 Page 2 of 5 Rev. 0

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

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months (Section 5.10) 2and/or Technical period and 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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-1:

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 Nuclear Common Page 3 of 6 Rev. 0

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

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Administrative TAS K: Evaluate a shift staffina situation and take corrective action lAW administrative nrncedures

STEP STEP COMMENTS

NO. (*Denotes a Critical Step) STANDARD 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 NAME:

JOB PERFORMANCE MEASURE 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)

11 Obtain signature or TELECON approval Locates number and calls or beeps Vice from DIRECTOR-OPERATIONS 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

12 Candidate indicates he/she would now call Ed Gallagher with approval for exceeding the "Working Hours Guideline" 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 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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) 5.9 Operating 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.

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]

5.10 Working Hour Guidelines

[CD-093D, HC/SA T/S - 6.2.2]

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 0.0111 hours 6.613757e-5 weeks 1.522e-5 months work weeks while the units are operating.

Continued on next page Nuclear Common Page 11 of 49 Rev. 11

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 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight (excluding shift turnover time).

"* An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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 Page 12 of 49 Rev. 11

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

_ _FORM - I WORKING HOUR GUIDELINE DEVIATION / AUTHORIZATION I

Working Hour Guideline Deviation / Authorization Code Table Guideline Code Description 1 More than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in a work period 2 More than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period 3 More than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in a 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period 4 More than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any seven day period 5 Less than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months off between work periods NAME Code Justification Last Next Scheduled Scheduled Day Off Day Off t Dr / I, t

_____ 1)( S ,QO(44744 Requesting Supervisor (sign) b~ate Requesting Supervisor (print) 6AAm' i oA7'r& Jtdv.5 4AtO CAR/c" 4FAJ(TI4L-. Qlet c~l lCI*6C Department Manager (s~n) Date Department Manager (print)

Director - Operations (sign) Date 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 Page 49 of 49 Rev. 11

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

ATTACHMENT 10 SALEM SHIFT COMPLEMENT (Page 1 of 2)

[CD-419Y, T/S-6.2.21 Salem Unit 1 Mode 1-4 1-4 5-6, D 5-6, D Salem Unit 2 Mode 1-4 5-6, D 1-4 5-6, D OS 1 1 1 1 CRS 2 2 2 1 STA 1 1 1 I&

OSCC 1 1 1 RO/PO 5* 4 4 3 NEO 6# 5 5 5 Communicator 2 2 2 2 CD-252X Shift Electrician 1 1 1 1 CD-252X Shift I&C Technician 1 1 1 1 CD-252X RP Technician 2 2 2 2 CD-252X Chemistry Technician 1 1 1 1 Fire Brigade IAW ND.FP-AP.ZZ-0001 This attachment combines the minimum shift manning requirements of the Technical Specifications, Emergency Planning and Appendix R Simultaneous Alternate Shutdown. Clarifying statements pertaining to Technical Specification, Emergency Plan (EP), and Appendix R Simultaneous Alternate Shutdown manning are identified separately below.

NOTES FOR TECHNICAL SPECIFICATION MINIMUMS Except for the OS, the Shift Crew Composition may be one less than the minimum requirements for a period not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to accommodate the unexpected absence of on duty shift crew members provided that immediate action is taken to restore the Shift Crew Composition to within the minimum requirements of the tables. This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewperson's being late or absent.

During any absence of the OS from the Control Room area while the unit is in any MODE, an individual with a valid SRO License shall be designated to assume the Control Room Command Function.

At least one licensed Operator shall be in the Control Room of each unit when fuel is in the reactor. In addition, at least one licensed SRO shall be in the Control Room area at all times.

OS may fill the same position on Unit I and 2.

All CORE ALTERATIONS shall be observed and directly supervised by a licensed SRO who has no other concurrent responsibilities during this operation.

Continued on next page Nuclear Common Page 47 of 49 Rev. 11

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

ATTACHMENT 10 (Page 2 of 2)

Regarding RO minimums with both units in Modes 5-6, one of the two required individuals may fill the position on the other unit such that there are a total of three ROs for both units.

Regarding NEO minimums with both units in Modes 1-4, one of the three required individuals may fill the same position of Unit I and 2, such that there are a total of five NEOs for both units.

A site Fire Brigade of at least 5 members shall be maintained onsite at all times. The Fire Brigade shall not include 4 members of the minimum shift crew per unit necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency.

EMERGENCY PLAN MINIMUMS

& Individual who fulfills the STA requirement may fill the same position on Unit 1 and 2.

The CRS, if STA qualified, may fulfill the STA function when both units are in Mode 5, 6 or Defueled.

Indicates increase above the current EP requirement of four due to Tech Spec requirement to initiate callout for another RO to replace the RO from the unaffected unit.

Indicates increase above the EP requirements due to the provisions of having the NEO at each duty station including the CW/SW operator and radwaste operator.

NEOs may fill the Primary Communicator duty and ROs or NEOs may fill the Secondary Communicator duty. The Secondary Communicator position is manned by an RO from the unaffected unit when the EP is implemented, then at that time, Salem shall initiate callout procedures to replace the RO from the unaffected unit in accordance with the administration section of the Salem Unit's Tech Specs. The communicator duties may also be filled by qualified staff personnel. [CD-162F]

For each unaffected nuclear unit in operation, maintain at least one SRO, one Reactor Operator and one Nuclear Equipment Operator.

If needed, the Radiation Protection and Chemistry Technicians will be supplied by unaffected station on shift Radiation Protection and Chemistry Staff.

Positions associated with EP response will normally not be permitted to go below the minimum manning level. If due to illness or injury manning is below the minimum, the appropriate department management shall be contacted for corrective action.

The preferred action is to hold over the existing shift personnel until replacements are available. [CD-252X]

SIMULTANEOUS ALTERNATE SHUTDOWN [CR 970509099]

The manning required to perform Simultaneous Alternate Shutdown in the event of a fire is I - OS, 2 - CRS, I - STA, 4 - RO, 6 - NEO, 1 - Shift Electrician, and I - Shift I&C Technician.

Nuclear Common Page 48 of 49 Rev. 11

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

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 "R: See Questions IMPORTANCE FACTC )R:

APPLICABILITY: RO --- RO EO = RO L STA 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: N/A APPROVAL:

OPERATIONS BARGAINING UNIT TRAINING SUPERVISOR MANAGER REPRESENTATIVE 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: Minutes JPM PERFORMED BY: GRADE: F SAT r-] UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

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

QUESTION:

Both units are at 100% power when 1 R1 B-I, 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 - KE SENIOR REACTOR OPERATOR:

QUESTION #1 (2.1.12)

QUESTION:

Both units are at 100% power when 1 R1 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?

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 R1B-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

RESPONSE

REFERENCE:

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

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020913 S2 .OP-SO.CAV-0001(Q) 3.10 On an automatic start signal, the EACS fan in LEAD will start. If the LEAD fan fails to start, the STANDBY fan will start 30 seconds later due to low flow.

When only one train actuates ACCIDENT PRESSURIZED mode, only one EACS fan receives a start signal. If the fan receiving the start signal is the STANDBY fan, it will not start until the 30 second timer has timed out while sensing low flow indicating the LEAD fan did not start.

3.11 To reset a high radiation or SI actuation which shifts Control Room Ventilation into ACCIDENT PRESSURIZED mode, the CAV train in the unit which initiated the signal must be reset before the opposite Unit's CAV train can be reset.

3.12 IRIB and 2R1B with all four radiation monitoring detector channels (1R1B-1 and 2R1B-2 are located in Unit 1 Control Room Intake Duct. 2R1B-1 and 1R1B-2 are located in Unit 2 Control Room Intake Duct) are required for Control Room Envelope operability. If either monitor or any channel is blocked or otherwise inoperable, then entry into the applicable TSAS for &li Units is required JAW Technical Specification Table 3.3-6.

3.13 The Control Room ventilation radiation duct monitor block switches located on 2RP1 Panel block the high radiation alarm detected from 2R1B-1 (2RA17967) and 1R1B-2 (1RA17968), Radiation Detectors, located in the Unit 2 intake.

3.14 With the exception of alarms indicating radiation monitor BLOCKED, Unit 2 Control Room radiation alarms associated with the Control Room Ventilation System are for radiation monitor 2RIB-1 (located in Unit 2 Control Room Intake Duct) and 2R1B-2 (located in Unit I Control Room Intake Duct).

3.15 Radiation monitoring detectors in the Control Room Intake Ducts are located between the CAA40 and CAA43 inlet dampers. When either Control Room Intake Duct inlet damper is isolated (i.e. ACCIDENT PRESSURIZED mode, FIRE OUTSIDE CONTROL AREA mode, or manually) the detectors are considered inoperable because they are sensing only the air trapped between the dampers (Tech Spec Table 3.3-6, Action 28 is applicable).

3.16 When restoring Control Room Intake Duct inlet dampers, Technical Specification 3.0.6 is applicable for demonstrating OPERABILITY of radiation monitoring detectors.

3.17 Placing Control Room Ventilation System in FIRE INSIDE CONTROL AREA mode or FIRE OUTSIDE CONTROL AREA mode in one unit does NOT align the opposite unit.

The opposite unit should also be manually placed in FIRE INSIDE CONTROL AREA or FIRE OUTSIDE CONTROL AREA mode.

Salem 2 Page 5 of 62 Rev. 30

INSTRUMENTATION 3/4.3.3 MONITORING INSTRUEN-TATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm/trip setpoints within the specified limits.

APPLICABILITY: As shown in Table 3.3-6.

ACTION:

a. With a radiation monitoring channel alarm/trip setpoint exceeding the value shown in Table 3.3-6, adjust the aetpoint to within the limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or declare the channel inoperable.

b. With one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-6.

C. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREENTS 4.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CANNEL CMCX, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the modes I and at the frequencies shown in Table 4.3-3.

S LEN - UNIT I 3/4 3-35 Amendment No. 225

TABLE 3.3-6 (Continued)

RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE ALARM/TRIP INSTRUMENT MODES MEASUREMENT OPERABLE SETPOINT RANGE ACTION MODES SETPOINT RANGE ACTION

2. PROCESS MONITORS

b. Noble Gas Effluent Monitors I) Medium Range Auxiliary I I, 2, 3&4 *3.0x t0 2jtCiIc .j 3 10"j-101pCi/cm 3

23 Building Exhaust System (Plant Vent) (Alarm only)

2) High Range Auxiliary 3 I 1, 2, 3&4 2

<l.OxI0 pCI/cm 10"1LI05 pCi/CM3 Building Exhaust System 23 (Plant Vent) (Alarm only)

3) Main Steamline I/ I, 2, 3&4 <10 mR/hr Discharge (Safety MS Line 1_104 mR/hr 23 Valves and Atmospheric (Alarm only)

Steam Dumps)

4) Condenser Exhaust I System I, 2,3&4 51.27x 104 cpm 1-106 cpm 23 (Alarm only)

3. CONTROL ROOM

a. Air Intake 2/Intake#

Radiation Level *2.48x 103 cpm 10I_107 cpR, 24, 25 I

N# Control Room air intakes shared between Unit I and 2.

- ALL MODES and during movement of irradiated fuel assemblies and during CORE ALTERATIONS.

I SALEM - UNIT 1 3/4 3-36a Amendment No. 225

TABLE 3.3-6 (Continued)

TABLE NOTATION ACTION 19 - With the number of Channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 20 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.

ACTION 22 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.

ACTION 23 - With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirements, initiate the preplanned alternate method of monitoring the appropriate parameter(s),

within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

1) either restore the inoperable Channel(s) to OPERABLE status within 7 days of the event, or

2) prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

ACTION 24 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel(s) to OPERABLE status within 7 days or initiate and maintain operation of the Control Room Emergency Air Conditioning System (CREACS) in the pressurization or recirculation mode of operation. CORE ALTERATIONS and movement of irradiated fuel assemblies will be suspended during operation in the recirculation mode.

ACTION 25 - With no channels OPERABLE in a Control Room air intake, immediately initiate and maintain operation of the CREACS in the I pressurization or recirculation mode of operation. CORE ALTERATIONS and movement of irradiated fuel assemblies will be suspended during operation in the recirculation mode.

SALEM - UNIT 1 3/4 3-37 Amendment No. 225

PLAI-." SYSTEMS 3/4.7.6 00NP.ROL ROOM EMERGENCY AIR CON:!T:ON:NG SYSTEM LIMITING CONDITION FOR OPERATION

*====

* = ===

=* ===== ===== ===== ===== = = = = = == =

=

3.7.6 The common control room emergency air conditioning system (CREACS)*

shall be OPERABLE with:

a. Two independent air conditioning filtration trains (one from each unit) consisting of:

I. Two fans and associated outlet dampers,

2. One cooling coil,

3. One charcoal adsorber and FEPA filter array,

4. Return air isolation damper.

b. All other automatic dampers required for operation in the pressurization or recirculation modes.

C. The control room envelope intact.

APPLICABILITY: ALL MODES and during movement of irradiated fuel assemblies and during CORE ALTERATIONS.

ACTION: MODES 1, 2, 3, and 4

a. With one filtration train inoperable, align CREACS for single filtration train operation within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , and restore the inoperable filtration train to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With CREACS aligned for single filtration train operation and with one of the two remaining fans or associated outlet damper inoperable, restore the inoperable fan or damper to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

c. With the Control Room Envelope inoperable, restore the Control Room Envelope to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

d. With one or both series isolation damper(s) on a normal Control Area Air Conditioning System (CAACS) outside air intake or exhaust duct inoperable, close the affected duct within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one isolation damper secured in the closed position or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . (Refer to ACTION 27 of Table 3.3-6.)

The CREACS is a shared system with Salem Unit 1 SALEM - UNIT 2 3/4 7-15 Amendment No.173

PLANT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

e. With one or both isolation damper(s) on an outside emergency air conditioning air intake duct inoperable, close the affected duct within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one isolation damper secured in the closed position and restore the damper(s) to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

f. With any isolation damper between the normal CAACS and the CREACS inoperable, secure the damper in the closed position within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

MODES 5 and 6 or during movement of irradiated fuel assemblies and during CORE ALTERATIONS.

a. With one filtration train inoperable, align CREACS for single filtration train operation within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or suspend CORE ALTERATIONS and movement of irradiated fuel assemblies.

b. With CREACS aligned for single filtration train operation with one of the two remaining fans or associated outlet damper inoperable, restore the fan or damper to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or suspend CORE ALTERATIONS and movement of irradiated fuel assemblies. "

c. With two filtration trains inoperable, immediately suspend CORE ALTERATIONS and movement of irradiated fuel assemblies.

d. With the Control Room Envelope inoperable, immediately suspend CORE ALTERATIONS and movement of irradiated fuel assemblies.

e. With one or both series isolation damper(s) on a normal CAACS outside air intake or exhaust duct inoperable, immediately suspend CORE ALTERATIONS and movement of irradiated fuel assemblies until the affected duct is closed by use of at least one isolation damper secured in the closed position. (Refer to ACTION 27 of Table 3.3-6.)

f. With one or both series isolation damper(s) on an outside emergency air conditioning air intake duct inoperable, immediately suspend CORE ALTERATIONS and movement of irradiated fuel assemblies until the affected duct is closed by use of at least one isolation damper secured in the closed position. To resume CORE ALTERATIONS or movement of irradiated fuel assemblies, at least one emergency air intake duct must be operable on each unit.

g. With any isolation damper between the CAACS and the CREACS inoperable, immediately suspend CORE ALTERATIONS and movement of irradiated fuel assemblies until the damper is closed and secured in the closed position.

SALEM - UNIT 2 3/4 7-16 Amendment No.173 I

INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm/trip setpoints within the specified limits.

APPLICABILITY: As shown in Table 3.3-6.

ACTION:

a. With a radiation monitoring channel alarm/trip setpoint exceeding the value shown in Table 3.3-6, adjust the setpoint to within the limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or declare the channel inoperable.

b. With one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-6.

C. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the modes and at the frequencies shown in Table 4.3-3.

SALEM - UNIT 2 3/4 3-38 Amendment No. 206

TABLE 3.3-6 (Continued)

RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE ALARM/TRIP MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION

2. PROCESS MONITORS

b. Noble Gas Effluent Monitors 2 3 3

1) Medium Range Auxiliary 1,2,3&4 :3. Oxl0 pCi/cm 10-3-101 PCi/cm 26 Building Exhaust System (Alarm only)

(Plant Vent) 2 3 3

2) High Range Auxiliary 1,2,3&4 .1.0x10 pCi/cm I0"1-10 PCi/cm 26 Building Exhaust System (Alarm only)

(Plant Vent)

3) Main Steamline 1/ 1,2,3&4 10 mR/hr 1-104 mR/hr 26 Discharge (Safety MS Line (Alarm only)

Valves and Atmospheric Steam Dumps)

4) Cindenser Exhaust 1 1,2,3&4 *7.12x104 cpm 1-106 cpm 26 System (Alarm only)

3. CONTROL ROOM

a. Air Intake 2/Intake## S2.48x10 3 cpm 101-10" cpm 27,

- 28 1 Radiation Level

1. Control Room air intakes shared between Unit 1 and 2.

- ALL MODES and during movement of irradiated fuel assemblies and during CORE ALTERATIONS.

I SALEM - UNIT 2 3/4 3-39a Amendment No. 206

TABLE 3.3-6 (Continued)

TABLE NOTATION ACTION 23 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 24 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.7.1.

ACTION 25 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.

ACTION 26 - With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirements, initiate the preplanned alternate method of monitoring the appropriate parameter(s),

within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

1) either restore the inoperable Channel(s) to OPERABLE status within 7 days of the event, or

2) prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

ACTION 27 With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel(s) to OPERABLE status within 7 days or initiate and maintain operation of the Control Room Emergency Air Conditioning System (CREACS) in the pressurization or recirculation mode of operation. CORE ALTERATIONS and movement of irradiated fuel assemblies will be suspended during operation in the recirculation mode.

ACTION 28 - With no channels OPERABLE in a Control Room air intake, immediately initiate and maintain operation of the CREACS in the I

pressurization or recirculation mode of operation. CORE ALTERATIONS and movement of irradiated fuel assemblies will be suspended during operation in the recirculation mode.

SAE - UNIT 2 3/4 3-40 Amendment No. 206

GOLF GROUP NRC EXAMINATION ADMINISTRATIVE SECTION A.1 - CANDIDATE 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?

GOLF GROUP NRC EXAMINATION ADMINISTRATIVE SECTION A.1 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

RESPONSE

REFERENCE:

S2.OP-IO.ZZ-0003, Rev. 16, Step 5.3.15.H.3

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020920 S.OP-IO.ZZ-0003(Q) 5.3.12 COMPLETE Attachment 3, Section 2.0, Technical Specification

$ Surveillance Requirement 4.1.1.1.1 .c, SDM - Minimum Rod Height.

/4A 5.3.13 INITIATE Attachment 3, Section 3.0, Technical Specification Surveillance Requirement 4.1.1.4.a, Minimum Temperature for Criticality, at 15 minute intervals.

4* 5.3.14 IF criticality approach is interrupted for >4 hours, THEN INSERT all Control Rod Banks AND PERFORM Attachment 5, Section 2.0.

/#t5.3.15 INITIATE withdrawal of Control Banks with the following guidance:

/4 A. SELECT Manual using Rod Bank Selector Switch for normal withdrawal sequence (overlap).

AV4 B. Continuously MONITOR Nuclear Instrumentation during all withdrawals.

C. MONITOR IRPI for each rod for indication of rod withdrawal and rod bottom lights extinguish as rods are withdrawn.

D. MONITOR Group Step Counters for proper rod alignment and overlap.

E. INITIATE Attachment 3, Section 1.0

15 minutes prior to initiating withdrawal of Control Banks by recording the date and time Shutdown Rods are verified fully withdrawn.

F. Within 15 minutes of initiating Control Bank "A" withdrawal, COMPLETE Attachment 3, Section 1.0 by recording:

Date/Time any Control Bank rod is withdrawn At. Surveillance Results IAW stated Acceptance Criteria RECORD time of Mode 2 entry in the Control Room Narrative Log.

UPDATE WCM to Mode 2.

(step continued on next page)

SaleM2 Page 22 of 51 Rev. 16

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020920 s2 .oP-IO.ZZ-OOO3(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 RIL 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 pem, 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)

Salem 2 Page 23 of 51 Rev. 16

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020920 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 pem, 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:

550 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 10.10 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

CJ2

]INTEGRAL ROD WORTH (pcm) 00 k4co 97 105 115 125 128 133 5 143 15 153 25 163 35 173 45 183 55 0M 193 65 203 75 213 85 223 95 225 105 115 125 128 5 133 15 143 25 153 35 163 0 45 173 55 183 0-65 193 75 203 85 213 95 223 105 225 115 125 135 145 155 165 175 185 195 205 215 00 225 1

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

ObERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: ADMINISTRATIVE TASK: Review a completed surveillance procedure for a MDAFW Pump TASK NUMBER: 1230300302 JPM NUMBER: GOLF NRC - SRO A2 2.2.12 ALTERNATE PATH: LJ K/A NUMBER:

IMPORTANCE FACTOR: 3.0 3.4 APPLICABILITY: RO SRO EO = RO

STA

SRO W 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: V/A APPROVAL:

BARGAINING UNIT TRAINING SUPERVISOR OPERATIONS MANAGER REPRESENTATIVE 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: N/A JPM PERFORMED BY: GRADE: F]SAT R UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Nuclear Common Page 1 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 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 AUXILIARY 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)

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.

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

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

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: ADMINISTRATIVE TASK: Review a comDleted surveillance orocedure for a MDAFW PumD

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 ST.AF-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 NOTE 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-0310(Z)

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: ADMINISTRATIVE TAS K: Review a completed surveillance procedure for a MDAFW Pump STEP COMMENTS

NO. (*Denotes a Critical Step) EVAL (Required for UNSAT

(#Denotes a Sequential Step) SIU evaluation)

6 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*

7 Reviews Attachment 3 Notes 23 and 24AF21 are throttled, supplying feed to the SG's 8 Reviews Attachment 4 Reviews Section 1.0 for COMMENTS and 2.0 for SIGNATURES

9 Completes Section 5.3.2 Specifies that 5.3.2.C applies:

", Pump is operable

"* Initiate a change to increase test frequency lAW NC.WM-AP.ZZ 0003 NOTE: Evaluator has the option to terminate the JPM after this step 10 Complete Attachment 4, Section 3.0 Signs and dates 11 Forwards procedure to STA TERMINA TE 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 Page 4 of 5 Rev. 0

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020920 PSEG Internal Use Only Page 1_of 1 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 Attachment 2 - 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.

+ Attachment 1, 4.0 - added recording of Controlotron Data following zero adjustment.

+ Attachment 2, 2.0 - replaced Panametrics with Controlotron.

+ Attachment 2, 3.0 - replaced Panametrics with Controlotron.

IMPLEMENTATION REQUIREMENTS Effective Date/ 24 /

None APPROVED:

OperationlManager - Salem Date Sj

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020920 S.OP-ST.AF-ooo1(Q)

INSERVICE TESTING- 21 AUXILIARY FEED PUMP TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPOSE ................... .2

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

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 Attachment 1 Instrument and Test Equipment] )ata 14 Attachment 2 21 AF Pump Surveillance Data 16 Attachment 3 Independent Verification . 18 Attachment 4 Completion Sign-Off Sheet ... 19 S em2 Page 1 of 20 Rev. 14

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020920 s 2 .OP-ST.A-0001(Q) 1.0 PURPOSE 1.1 Provides instructions necessary to perform Inservice Inspection and Testing IAW Technical Specification 4.0.5 for the following components: [C02651

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. [C02651 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 PRER ElOUISITS t2.1 IDENTIFY sections of this procedure NOT to be performed with "N/A".

/< 2.2 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.

2*2.3 ENSURE the applicable SAP Order number(s) and Reason for Test are recorded on Attachment 1, Section 1.0.

/4/ 2.4 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. [C0583]

/* 2.5 ATTACH a copy of S2.RA-ST.AF-0001(Q), Inservice Testing 21 Auxiliary Feedwater Pump Acceptance Criteria.

Salem 2 Page 2 of 20 Rev. 14

-ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020920 S2 .OP-ST.AF-001(Q) 4 2.6 ENSURE Maintenance Technician is available to perform the following:

V 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.

1% 2.7 Direct Maintenance Technician to PERFORM the following:

PROGRAM the DLU Watchman DC-7 Data Collector to record 21 Auxiliary Feedwater Pump vibration. [C06001

/Iýt_

RECORD calibration data for the M&TE and Vibration Data Collection Equipment listed in Attachment 1, Section 2.0 and 3.0. [C0289]

lrv;t

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

/ 3.1 Procedure Use and adherence policy as found in NC.NA-AP.ZZ-0001(Q),

3.2, Nuclear Procedure System, is applicable to this procedure.

A 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.

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

3.5 21 AF Pump is to be stopped should the motor winding temperature exceed 266°F.

3.6 21 AF Pump oil levels are to be maintained at 1/2 to 3/4 full.

, 3.7 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. [C0270]

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

Sae2 Page 3 of 20 Rev. 14

-ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020920 S2.OP-.ST.AF-0001(Q) 4,ý 3.9 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.

lqz 3.10 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:

+ IA Master Key

4.3 Procedure(s)

+ Copy of S2.RA-ST.AF-0001(Q), Inservice Testing - 21 Auxiliary Feed Pump Acceptance Criteria S e2 Page 4 of 20 Rev. 14

-ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020920 S2.OP-ST.AF-0001(Q) 5.0 PROCEDURE 5.1 IST of 21 AF Pum

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

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

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.

/A - 5.1.3 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.

/1 5.1.4 ENSURE the following valves are OPEN:

A. 21AF101, AF PUMP RECIRC ISOL B. 21AF40, AF PMP RECIRC V i*/Y 5.1.5 IF in Modes 1-3, THEN ENTER T/S 3.7.1.2 for 21 Auxiliary Feedwater Pump.

Az& 5.1.6 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 START 21 AF Pump.

17"z 5.1.8 ENSURE 21AF40, AF PMP RECIRC V, modulating valve is OPEN.

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

AND VENT air supply at regulator petcock.

Salem2 Page 5 of 20 Rev. 14

-ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020920 s 2 .oP-sT.AF-ooo1(Q)

/*" 5.1.10 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. I 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".

/* 5.1.11 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.

1AZ 5.1.12 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:

PRINT 21 Auxiliary Feedwater Pump vibration results.

4 2. 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.

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

Salem 2 Page 6 of 20 Rev. 14

-ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020920 s 2 .OP-ST.AF-0001(Q) 5.1.13 POSITION 21AF40 handwheel to NEUTRAL AND LATCH handwheel.

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

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

5.1.16 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]

7.._

f 5.1.17 PLACE Controlotron Power Supply Switch to OFF position. I

/~-5.1.18 IF 21 AF Pump is required to maintain steam generator water level, THEN ADJUST the valve demands to the following valves, as required:

4 23AF21, STEAM GENERATOR INLET VALVE

24AF21, STEAM GENERATOR INLET VALVE

/*g 5.1.19 PLACE No. 2 Aux Feed Tank Heater Pump in AUTO.

A10' 5.1.20 IF in Modes 1-3, THEN EVALUATE T/S 3.7.1.2 for continued applicability.

/***5.1.21 Direct a second Operator to PERFORM Independent Verification of the following:

Calculations performed in Attachment 2. [C0284]

Valve positions in Attachment 3. [C0290]

Salem 2 Page 7 of 20 Rev. 14

-ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020920 S2 .OP-ST.AF-0001(Q)

__/ 5.1.22 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.

A/IA 5.1.23 IF this surveillance is being performed to establish new baseline data,

$ THEN IST Implementation Engineer PERFORM the following:

AJ/4 A. EVALUATE the data AND DETERMINE if the specified components IST meet minimum design requirements.

A)/14 B. RECORD "Test Results" by initialing SAT or UNSAT column using

$ IST the Acceptance Criteria in Attachment 2, Sections 1.0, 2.0 and 3.0.

Salem 2 Page 8 of 20 Rev. 14

-ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020920 S.OP-ST.AF-O01 (Q) 5.2 Acceptance Criteria S5.2.1 This surveillance is satisfactory when Attachment 2 is completed with equipment listed meeting the Technical Specification Acceptance Criteria (ASME) stated in the attachment.

OR A) (I4 5.2.2 This surveillance is unsatisfactory.

SA. INITIATE NOTF(s) to correct unsatisfactory condition(s).

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

5.3 Completion and Review 01A)PATE 5.3.1 COMPLETE Attachment 4, Sections 1.0 and 2.0, AND FORWARD this procedure to the CRS for review.

"AAAW 5.3.2 CRS PERFORM the following:

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

LýI-IAA JP4 ,XAl B. IF all pump Technical Specification Acceptance Criteria (ASME) parameters are SAT AND in the ACCEPTABLE RANGE, THEN:

44*, DECLARE Pump OPERABLE.

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

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

Inservice Testing Program.

C--,-- 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:

(Q'WP76* DECLARE pump OPERABLE.

('AAMie-j.

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

-ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020920 s 2 .OP-ST.AF-0001(Q) 5.3.2 (continued)

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 NOTW 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 lAW NC.WM-AP.ZZ-OOOO(Q),

Notification Process.

- RECORD NOTF 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:

- INITIATE a NOTF IAW NC.WM-AP.ZZ--000(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)

Salem 2 Page 10 of 20 Rev. 14

-ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020920 s 2 .OP-ST.AF-0001(Q) 5.3.2 (continued)

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

_ DECLARE the Check Valve inoperable.

+ EVALUATE Technical Specifications for system operability.

+ INITIATE a NOTF IAW NC.WM-AP.ZZ-O000(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.

5.3.3 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.

5.3.4 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.

END OF PROCEDURE SECTION Salem 2 Page 11 of 20 Rev. 14

-ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020920 s 2 .OP-ST.AF-0001(Q) 6.0 RECORDS 6.1 Retain the following IAW NC.NA-AP.ZZ-0011(Q), Records Management Program:

Attachment 1-4

+ 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 Sa em2 Page 12 of 20 Rev. 14

-ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020920 s 2 .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 Salen12 Rev. 14 Page 13 of 20

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020920 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

[SAP O N r:Scheduled Surveillance C

4* " /0 )-l/ 4) Post-Maintenance Operability Establish New Baseline Data Other (Explain in Comments) 2.0 VIBRATION DATA COLLECTION EQUIPMENT:

Instrument/Test II Description Calibration Initials Equipment Due Date I)1//

[)-/

- P67 - 495-T- -r DLI Watchman DC-7 Data Collector DLI Triaxial Accelerometer 3 -."

(23 3.0 TEMPORARY TEST EQUIPMENT IID Number & In ll Point Installation Removal Temporary Test Equipment Cal. Due Date Initials IDate Initials Date Heise CM or # t(2?Qo,7 Instr. Vent for .4 equivalent 2PL8647 0-60 psig Date: 1-/9- .3 (suction pressure) (1)(2)

Heise CM or # (0 0 . Instr. Vent for equivalent 2PLI678 Vnf 0-3000 psig [Date:/, . (discharge pressure)

(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.

Sae2 Page 14 of 20 Rev. 14

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020920 S2 .OP-ST.AF-0001(Q)

ATTACHMENT 1 (Page 2 of 2)

INSTRUMENT AND TEST EQUIPMENT DATA 4.0 CONTROLOTRON DATA Description ID Number Calibration Overdue Date Controlotron 2FL14752 1.2- 12 SC.IC-DC.ZZ-0003(Q), Controlotron Model 960 and 990 Flow Computer Zero Adjustment has been completed.

Performed By:___ __ _ Date: Time: / ,

5.0 POST TEST CALIBRATION RESULTS Instrument/Test ID Number SAT UNSAT Initials Equipment Heise CM or equivalent 0-60 psig (1)

Heise CM or equivalent 0-3000 psig 44 (i)

(1) Post-Test Calibration is NOT required when Electronic Pressure Modules (digital) are used.

Performed by Date M&TE Technician Performed by Date M&TE Supervisor Salem2 Page 15 of 20 Rev. 14

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020920

.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 IA * / " in/sec (1)

Vibration Position 1H in/sec (1)

Vibration Position 1V L2f in/sec (1)

Vibration Position 2A in/sec (1)

Vibration Position 2H in/see (1)

Vibration Position 2V , in/sec (1)

Vibration Position 3A o/4ff in/sec (1)

I Technical Specification Acceptance Criteria (ASME)

$ Vibration Position 3H in/sec (1)

$ Vibration Position 3V in/sec (1)

$ Vibration Position 4A $3 in/seC (1)

$ Vibration Position 4H in/sec (1)

$ Vibration Position 4V / 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.

Salem 2 Paze 16 of 20 Zev. 14

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020920 S2 .OP-ST.AF-0001(Q)

ATTACHMENT 2 (Page 2 of 2) 21 AF PUMP SURVEILLANCE DATA 2.0 PUMP PERFORMANCE DATA:

F' 1]

Pump Discharge Pressure (Heise Gauge)

Differential Pressure (B) - (A)

I Technical Specification Acceptance Criteria (ASME):

Measured values are within bands specified in S2.1RA-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: 4 dt [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 SPARTIAL Acceptable Range of S2.RA-ST.AF-0001(Q),

21AF4 OPEN Inservice Testing - 21 Auxiliary Feedwater Pump Acceptance Criteria, as indicated on the Controlotron.

I Salem 2 Page 17 of 20 Rev. 14

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020920 S2.OP-ST.AF-0001(Q)

ATTACHMENT 3 (Page I of 1)

INDEPENDENT VERIFICATION Component Description Normal Position IV 21AF40 AF PMP REC1RC 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 X 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.

Salem 2 Page 18 of 20 Rev. 14

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020920 S.OP-ST.AF-O01I(Q)

ATTACHMENT 4 (Page 1 of 2)

COMPLETION SIGN-OFF SHEET

1.0 COMMENTS

(Include test deficiencies and corrective actions.)

Salem 2 Page 19 of 2fl 130- 1A JL*.*T D .IL*qF

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020920 S2.OP-ST.AF-0001(Q)

ATTACHMENT 4 (Page 2 of 2)

COMPLETION SIGN-OFF SHEET

2.0 SIGNATURES

Print Initials Sigý3Wre Date IA/

Zz4',4cIfit r INDEPENDENT VERIFICATION:

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]

Signature: Date:

CRs Signature: Date:

STA Signature: Date:

OS/CRS 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.

Signature: Date:

IST Implementation Engineer Salem 2 Page 20 of 20 Rev. 14

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020701 PSEG Internal Use Only IST GROUP Page I of 1 S2.RA-ST.AF-0001(Q) - REV. 5 INSERVICE TESTING 21 AUXILIARY FEED PUMP ACCEPTANCE CRITERIA 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 Date APPROVED:

AL-L ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE--

20020701 S2.RA-ST.AF-OOOl(Q)

INSERVICE TESTING 21 AUXILIARY FEED PUMP ACCEPTANCE CRITERIA TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPOSE...................

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

2 .° 3.0 PRECAUTIONS AND LIMITATIONS 2 ..

4.0 EQUIPMENT/MATERIAL REQUIRED 2 ..

5.0 PROCEDURE................

2 .° 6.0 RECORDS..................

3 .°

7.0 REFERENCES

3 .° ATTACHMENTS Attachment 1 21 AF Pump Surveillance Data Acceptance Criteria ...............

5 Salem2 Page 1 of 6 Rev. 5

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

20020701 S2 .RA-ST.AF-0001(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 PREREQUISITES None 3.0 PRECAUTIONS AND LIMITATIONS None 4.0 EQUIPMENT/MATERIAL REQUIRED None 5.0 PROCEDURE None END OF PROCEDURE SECTION Salem 2 Page 2 of 6 Rev. 5

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

20020701 S2.RA-ST.AF-miO(Q) 6.0 RECORDS None

7.0 REFERENCES

7.1 UNdated 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 Drawing 7.3.1 205336, No. 2 Unit Auxiliary Feedwater 7.4 Procedur es:

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 20020701 S2 .RA-ST.AF-oool(Q)

7.5 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-0001(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 A _0 Ijt ll Ug7, Rev. 5

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020701 s 2 .RA-ST.AF-ooo(Q)

ATTACHMENT 1 21 AF PUMP SURVEILLANCE DATA ACCEPTANCE CRITERIA (Page I of 2) 1.0 PUMP VIBRATION READINGS:

21 AF Pump Rererence Acceptance Alert Required Vib. Pos. Value Date (in/see) Range Range Action Range SAT SAT UNSAT 1A (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 2H (2) 0.18 0.0 0.324

- > 0.324 - 0.700 > 0.700 2V (2) 0.09 11/14/1999 0.0 0.225

- > 0.225 - 0.540 > 0.540 3A (2) 0.44 (1) 0.0 - 0.640 > 0.640 - 0.765 > 0.765 3H (3) 0.53 I 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 44H (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 Rev. 5

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020701 S2.RA-ST.AF-O001(Q)

ATTACHMENT 1 21 AF PUMP SURVEILLANCE DATA ACCEPTANCE CRITERIA (Page 2 of 2) 2.0 PUMP HYDRAULIC DATA:

(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 ___ 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 > 1369 psid LAW F-C-AF-MDC-0445, Rev 2, Auxiliary Feedwater Hydraulic Analysis.

Salem 2 Pa,76 6af

-- *v v v* v . a eV.

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

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: ADMINISTRATIVE (Waste Gas)

TASK: Review a radioactive gaseous waste release form TASK NUMBER: 0710050302 JPM NUMBER: GOLF NRC - SRO A3 ALTERNATE PATH: K/A NUMBER: 2.3.6 IMPORTANCE FACTOR: 3.1 APPLICABILITY: RO SRO EO = RO - STA

SRO L-I 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: N/A APPROVAL:

BARGAINING UNIT TRAINING SUPERVISOR OPERATIONS MANAGER REPRESENTATIVE 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: N/A Minutes JPM PERFORMED BY: GRADE: D SAT DUNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Nuclear Common Page 1 of 5 Rev. 0

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

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: ADMINISTRATIVE (Waste Gas)

TASK: 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 the paperwork.

3. The release will continue until 12 Gas Decay Tank is completely depressurized in order to allow replacement of the relief valve

4. RMS Channel 1R41 D is inoperable SIMULATOR SETUP: N/A 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.

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-031 0(Z)

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: ADMINISTRATIVE (Waste Gas)

TASK: Review a radioactive gaseous waste release form PSTEP COMMENTS

(*Denotes a Critical Step) 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 Attachment 2 completed up to the that the other sections of S1.OP-SO.WG OS/CRS signature line 0009 have been completed properly.

START TIME:

Attachment 2 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 Page 3 of 5 Rev. 0

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

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE 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) 5 Ensure Section 4.0 (RELEASE REVIEW Verifies release rate >32 SCFM AND APPROVAL-Operations) completed NOTE: If at the plant or in the simulator, correctly the Evaluator can elect to have the candidate point out the indication related to 4.2 and 4.3 CUE: The information in 4.2, Ventilation Configuration, and 4.3, Radiation Monitor Release Data/Source Check/Channel Operable, matches indications 4.5 - Does NOT sign* - returns to Chemistry for corrective action 6 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 Page 4 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 initiated the paperwork.

3. The release will continue until 12 Gas Decay Tank is completely depressurized in order to allow replacement of the relief valve

4. RMS Channel 1 R41 D is inoperable 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.

Nuclear Common Page 5 of 5

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020801 PSEG Internal Use Only Page 1 of 3 PSEG NUCLEAR L.L.C.

SALEM/OPERATIONS SI.OP-SO.WG-0009(Q) - REV. 25 DISCHARGE OF 12 GAS DECAY TANK TO PLANT VENT USE CATEGORY: I REVISION

SUMMARY

Biennial Review Performed: Yes _V_ No NA

The following changes to this procedure are incorporated IAW Technical Specification Amendment 234. (80018643)

"* 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, 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, Gaseous Effluents, to the Offsite Dose Calculation Manual.

"* Added Step 3.8 - to provide program requirement guidance for the changes implemented by Technical Specification Amendment 234.

"* 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 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, to references.

IMPLEMENTATION REQUIREMENTS Effective Date_____

+ Technical Specification Amendment 234 APPROVED:

V ations Manager - Salem Date

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020801 PSEG Internal Use Only Page 2 of 3 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.

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 Si.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.

Step 5.3.1 - added step to complete and attach additional chemistry paprerwork.

"* Attachment 5, Section 3.0 - deleted the step to forward procedure to Technical Supervisor - Chemistry for completion.

"* Attachment 2, Sections 2.0 and 3.0 - revised to align with SC.CH-TI.ZZ-0146(Q).

"* Attachment 2, Old Section 3.0 - deleted Dose Estimates table. Data redundant to Radioactive Gaseous Release Initiation Form.

"* Attachment 2, Step 6.0 - deleted Chemistry signoff.

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020801 PSEG Internal Use Only Page 3 of 3 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):

Upgraded to the latest administrative standards.

"* Changed "NCO" to "RO/PO."

"* Deleted WG MECH 001 - Gaseous Waste Disposal System Mechanical System Alignment, from references.

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.

Changed NC.NA-AP.ZZ-0003(Q), Document Management Program, to NC.NA-AP.ZZ-001 I(Q), Records Management Program.

+ Note prior to Step 5.2.1 .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.l.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. (R22342)

Step 5.1.3 - added to provide a termination path if the release is not to be completed.

(80019587)

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020801 Sl.OP-SO.WG-0009(Q)

DISCHARGE OF 12 GAS DECAY TANK TO PLANT VENT TABLE OF CONTENTS SECTION TITLE PAGE 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 Preparation 5.2 12 Gas Decay Tank Release ....

5.3 Completion and Review ....... 10 6.0 RECORDS .................... 11

7.0 REFERENCES

.................. 11 ATTACHMENTS Attachment 1 12 Gas Decay Tank Alignment/Ver fication 14 Attachment 2 12 GDT Radioactive Gaseous Relea se Form 16 Attachment 3 12 GDT Release Rate Calculation 22 Attachment 4 Plant Vent Flow Rate Discharge Esitimation 23 Attachment 5 Completion/Sign-Off Sheet ..... 24 saleml Page 1 of 25 Rev. 25

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020801 SI.OP-SO.WG-0009(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 2.1 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.

2.2 The following systems are in service:

2.2.1 Auxiliary Building Ventilation IAW S1.OP-SO.ABV-0001(Q),

Auxiliary Building Ventilation Operation 2.2.2 Fuel Handling Building Ventilation System IAW S1.OP-SO.FHV-0001(Q),

Fuel Handling Building Ventilation Operation.

2.3 ENSURE Noble Gas Activity Monitor (IR41A & D OR 1R16) are OPERABLE (IAW the ODCM).

2.4 ENSURE Plant Vent Flow Rate Monitor and Sample Flow Rate Monitor are OPERABLE (IAW the ODCM).

2.5 ENSURE Noble Gas Activity Monitor 1R41A & D is OPERABLE (IAW the ODCM).

2.6 ENSURE Iodine Sampler and Particulate Sampler (Chemistry Dept.) are OPERABLE (LAW 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.

3.2 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.

Salem I Page 2 of 25 Rev. 25

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020801 SI.oP-SO.WG-0009(Q) 3.5 DO NOT transfer Waste Gas from one GDT to another during the GDT release.

3.6 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.

3.7 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).

3.8 The program requirements of Radiological Effluent Technical Specifications (RETS) are located in the Offsite Dose Calculation Manual (ODCM) and Process Control Program (PCP). (80018643) 3.9 Inoperability of the Noble Gas Activity Monitor (1R16, 1R12A, IR41A & D), Iodine Sampler, Particulate Sampler, Flow Rate Monitor, or Sampler Flow Rate Monitor for

> 30 days is reportable JAW NC.WM-AP.ZZ-0002(Q), Performance Improvement Process (IAW the ODCM).

3.10 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 Salem I Rev. 25 Page 3 of 25

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020801 Si.OP-SO.WG-0009(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 IAW this procedure.

B. PERFORM 12 GDT Holdup Alignment IAW Attachment 1, Section 1.0. I C. DIRECT second operator to complete Independent Verification (IV) of 12 GDT Holdup Alignment IAW Attachment 1, Section 1.0.

5.1.2 INITIATE 12 GDT Radioactive Gaseous Release Form as follows:

A. COMPLETE Attachment 2, Section 1.0.

B. FORWARD entire procedure to Chemistry Department for completion of Attachment 2, Sections 2.0 and 3.0.

5.1.3 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.

Salem 1 Rev. 25 Page 4 of 25

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020801 Sl.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 LAW the ODCM:

A. IF 1R41A & 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 (LAW 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 IR16 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , AND ANALYZE for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

B. PLACE 1ND17572 - 1WG41 Waste Gas Decay Tank in BLOCK.

Sae I Page 5 of 25 Rev. 25

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020801 sl.OP-SO.WG-00g(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 (lAW 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months IAW 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months IAW SC.CH-AB.ZZ-1102(Q) and the ODCM.

5.2.7 PERFORM Pre-Release Verification of 12 GDT Holdup Alignment IAW Attachment 1, 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. I 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)

Sae I Page 6 of 25 Rev. 25

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020801 S1.OP-SO.WG-0009(Q) 5.2.11 (continued)

D. LATCH AND SET LWG41, GDT VENT CONT VALVE, as follows:

NOTE 1WG41 Controller (1HIC-14) must be set to <0% or 1WG41 will NOT latch.

S1. 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 > 100%.

NOTE 1W!G41 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 IWG41 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

ROIPO Initials I G. OPEN 12WG31, GDT INLET VALVE.

(step continued on next page)

Salem 1 Page 7 of 25 Rev. 25

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020801 S1.OP-SO.WG-0009(Q) 5.2.11 (continued)

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)

H. Slowly OPEN 12WG34.

S.. 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 IWG41 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 Attachment 1, 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 Attachment 3, 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 Attachment 4 at least once every four hours during GDT release.

(step continued on next page)

Salem 1 Page 8 of 25 Rev. 2 5$

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020801 Si .OP-SO.WG-0009(Q) 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 IWG41 CLOSES, THEN TERMINATE the GDT release as follows:

1. TURN IWG41 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 JAW Attachment 1, Section 5.0.

Salein I Page 9 of 25 Rev. 25

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020801 Sl.OP-SO.WG-0009(Q) 5.3 CMpletion 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 and 2.0, 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 1-5 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

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020801 Si.OP-SO.WG-0009(Q) 6.0 RECORDS 6.1 Retain entire procedure lAW NC.NA-AP.ZZ-0011(Q), Records Management Program.

7.0 REFERENCES

7.1 Salem Generating Station Updated Final Safety Analysis Repor:

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 S1.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 SI.OP-SO.CA-0001(Q), Control Air System Operation 7.3.8 S1.OP-SO.CVC-0010(Q), Establishing VCT Atmosphere 7.3.9 S1.OP-SO.FHV-0001(Q), Fuel Handling Building Ventilation Operation 7.3.10 S1.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 SI.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 Salem I Page 11 of 25 Rev. 25

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020801 Sl.OP-SO.WG-0009(Q)

7.5 Others

7.5.1 DCP IEE-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-WGO01-01, Salem Unit 1, 2 Gas Decay Tank Pressure - Alarm and Recorder (Setpoint Calc & Scaling) 7.5.12 10CFRS0, 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 Salem 1 Page 12 of 25 Rev. 25

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020801 SI.OP-SO.WG-0009(Q)

7.6.4 Procedures

A. NC.NA-AP.ZZ-0001(Q), Nuclear Procedure System B. NC.NA-AP.ZZ-0011(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 Salem 1 Rev. 25 Page 13 of 25

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020801 sl.OP-SO.WG -009(Q)

ATTACHMENT 1 (Page 1 of 2) 12 GAS DECAY TANK ALIGNMENT/VERIFICATION 1.0 PRE - RELEASE ALIGNMENT/VERIFICATION VALVE DESCRIPTION POSITION INITIALS INITIALS RELEASE VERILF 12WG31 GDT INLET V *CLOSED 12WG32 GDT PRESS TAP OPEN 11WG34 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 IWG81 WG VENT PRESS TAP OPEN

[CWG317 GDT PRESS TRANS V OPEN

[C0317]__ _ _ _ _ _______ ______ __ _ _ _ _

Cleared and Tagged for CRS.

2.0 1WG41 VALVE POSITION CONTROLLER VALVE NO. DESCRIPrTION POSITION IV INITIALS 1WG41 GDT VENT CONT V 0%

Salem I Page 14 of 25 Rev. 25

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020801 SI.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 IWG41 WASTE GAS DECAY NORMAL TANK Saldem 1 Page 15 of 25 Rev. 25

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020801 Si.OP-SO.WG-0009(Q)

ATTACHMENT 2 (Page 1 of 6) 12 GDT RADIOACTIVE GASEOUS RELEASE FORM RELEASE NO. .26Z "-_4A11 1.0 SAMPLE REQUEST (Operations) 1.1 12 GDT has not been added to since (time) e)_1 __ (date)--*P ,9X / 6 and is at ____, PSIG as indicated by 1PIS1037.

6 1.2 A pre-release sample of 12 GDT and release rate computation is requested.

Signature: Date " ,)lv/

2.0 SAMPLE POINT (Chemistry)

/ 2.1 PERFORM gaseous discharge process IAW SC.CH-TI.ZZ-0146(Q),

Radiological Gaseous Effluent Discharges.

_ 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

___ INDICATE if the following instruments are in service for release:

INSTRUMENTATION IN SERVICE Iodine Sampler Particulate Sampler Sampler Flow Rate Monitor Salem 1 Rev. 25 Page 16 of 25

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020801 Sl.OP-SO.WG-0009(Q)

ATTACHMENT 2 (Page 2 of 6) 12 GDT RADIOACTIVE GASEOUS RELEASE FORM RELEASE NO. ,_,______

3.0 DOSE, VOLUME ESTIMATES AND APPROVAL (continued) 6Z *

3.2 Pressure

COMPLETE the following required data for 12 GDT:

Isolated Pressure ___/ __ (PSIG)

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.

Estimated Final Pressure /. (PSIG)

3.3 Volume

/l

ESTIMATE total volume of Waste Gas to be released:

9, 26/6i3 (CUFT)

Sae 1 Page 17 of 25 Rev. 25

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020801 SI.OP-SO.WG-0009(Q)

ATTACHMENT 2 (Page 3 of 6) 12 GDT RADIOACTIVE GASEOUS RELEASE FORM RELEASE NO. 2662 -" A1 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 <5-32 SCFM cannot be released.

- Approval is granted to r lease 12 GDT at the Calculated Maximum Allowable Release Rate of SCFM.

/** This Release is consistent with the Limits set forth in the Offsite Dose Calculation Manual.

_Z IF RMS Channel 1R41A or D is inoperable, THEN the following have been completed (lAW the ODCM):

A. At least two independent samples of 12 GDT contents have been analyzed.

B. Release rate calculations have been independently verified by at least two technically qualified members of the Facility Staff.

C. IF RMS Channel 1R16 is inoperable, THEN grab samples are being obtained at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , AND analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

IF Iodine SamplerS* or Particulate Sampler is inoperable, THEN a continuous sample of the effluent release pathway is being collected with auxiliary sampling equipment IAW SC.CH-AB.ZZ-1 102(Q), Response to Inoperable Technical Specification Effluent Monitors and Equipment.

7/*

IF Sampler Flow Rate Monitor is inoperable, THEN flow rate is being estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months IAW SC.CH-AB.ZZ-1102(Q), Response to Inoperable Technical Specification Effluent Monitors and Equipment.

((

All Chemistry requirements for 12 GDT release to the Plant Vent are satisfied and authorization given.

Signature::-,,' Time *,L Date Chemistry I !

At'

FORWARD this Radioactive Gaseous Release Form to OS/CRS.

Salem I Page 18 of 25 Rev. 25

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020801 SI.OP-SO.WG-0009(Q)

ATTACHMENT 2 (Page 4 of 6) 12 GDT RADIOACTIVE GASEOUS RELEASE FORM RELEASE NO. *6eQ2""

4.0 RELEASE REVIEW AND APPROVAL (Operations) 4.1 Release Verification:

Q/t6Calculated Maximum Allowable Release Rate from Section 3.4:

Lt SCFM.

ýý- 0 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 ___

/ 1 61t 4.3 Radiation Monitor Release Data/Source Check/Channel Operable:

Time Date Radiation Monitor Source Check I Monitor Prior to Release 4 imaY laio 1R16 OPCPM

/Ž,-5 7I,, 1R41A P OP /, 62, pCi/cc

jp,,y I 1R41D N/A gzCi/sec 4.4 Release Review

-ýýTime Date <0'4y RO/PO I 4.5 All requirements in Section 3.0 and subsections 4.1 thru 4.4 are met to authorize the release of the tank.

Time Date OS/CRS I Salem 1 Rev. 25 Page 19 of 25

Public Service Electric and Gas EMS 20371.172.002.G Salem Generating Station Unit # 1 BATCH GASEOUS EFFLUENT PERMIT Allocationl00.%

I. REQUEST:

X NORMAL POINT OF RELEASE ESTIMATED START:

UNPLANNED #12 Waste Gas Decay Tank 01-jul-2002 09:30:00 RELEASE VOLUME (EST.) POINT OF DISCHARGE ESTIMATED STOP:

3.2143E+03 CF Unit #1 Plant Vent 01-jul-2002 11:10:27 II. SAMPLE IDENTIFICATION:

NUMBER COLLECTION DATE/TIME ANALYSIS DATE/TIME 428 21-jun-2002 10:50:00 21-jun-2002 10:57:20 Noble Gas File Name : CAS SAM:20020621005_ADC2_WGDT.CNF Particulate File Name: N/A Radioiodine File Name: N/A III. RADIOANALYSIS - GASEOUS:

CUMULATIVE DOSES AIR DOSE BETA(M) AIR DOSE GAMMA(M) ORGAN DOSE(M) 1.36E-04 mrad < 1.25 1.21E-06 mrad < 0.63 1.35E-03 mrem < 1.88 AIR DOSE-BETA(Q) AIR DOSE-GAMMA(Q) ORGAN DOSE(Q) 1.36E-04 mrad < 10.00 1.21E-06 mrad < 5.00 1.35E-03 mrem < 7.50 AIR DOSE-BETA(A) AIR DOSE-GAMMA(A) ORGAN DOSE(A) 9.43E-03 mrad < 20.00 2.72E-03 mrad < 10.00 8.70E-03 mrem < 15.00 YEARLY DOSE RATES T-BODY DOSE RATE 5.92E-03 mrem/yr < 500.00 SKIN DOSE RATE 4.98E-01 mrem/yr < 3000.00 ORGAN DOSE RATE 1.70E-02 mrem/yr < 1500.00 IV. RADIATION MONITOR(S):

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -.7 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -.

NUMBER MAX SETPOINT ALERT SETPOINT EXPECTED RESPONSE IR41D (NG) 2.OOOE+04 uCi/s 1.OOOE+04 uCi/s 1.665E+02 uCi/s 1R41D (NG) 1.227E+12 uCi/s 6.137E+11 uCi/s V. AUTHORIZATION:

MAX. VOLUME MAX. EFFLUENT FLOW RATE 3.2143E+03 CF 3.2000E+01 CFM The above-named source has been sampled and analyzed and is in compliance with the Offsite Dose Calculation Manual. Release is authorized for the volume and flow rates specified.

Please Return Permit to Chemistry Upon Completion

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020801 S1.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:

IPL8678 PSIG*

Shall be maintained .8.0 psig to ensure GDT release rate r32 SCFM.

PERFORM an Independent Verification of:

1WG38 pressure (1PL8678) <r8.0 psig.

IV

1WG41 controller positioned

100% (corresponds to a maximum IV gaseous release rate of

32 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 ° at El.

.*T( 1 - 33') C*

Salem 1 Page 20 of 25 Rev. 25

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020801 Sl.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:

Radiation Monitor Highest Reading 1PIS1037 I during release 1R16 CPM PSIG 1R41A I Ci/cc 1R41D i uCi/sec I

_ Plant Vent Flow during Release (average):

SCFM 5.4 12 GDT Radioactive Gaseous Release conducted under supervision of:

Date.

(OS/CRS)

Salem 1 Page 21 of 25 Rev. 25

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020801 S1.OP-SO.WG-0009(Q)

ATTACHMENT 3 (Page 1 of 1) 12 GDT RELEASE RATE CALCULATION Initial Pressure = psig (1PIS1037) Time 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 Initial GDT Pressure- GDT Pressure Average Release Rate =

Time (Min)

Maintain Average Release Rate *5 1.0 psig/min by reducing IWG41 valve position.

Average Release Rate at end of GDT release shall NOT exceed 1.0 psig/min (IAW the ODCM). I Salem I Rev. 25 Page 22 of 25

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020801 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 # 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Estimated Time Date Plant Vent Flow Rate SCFM SCFM SCFM SCFM SCFM SCFM Salem 1 Rev- 25 Page 23 of 25

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020801 Sl.OP-SO.WG-0OO9(Q)

ATTACHMENT 5 (Page 1 of 2)

COMPLETION SIGN-OFF SHEET

1.0 COMMENTS

(Include procedure deficiencies and corrective actions.)

Salem 1 Page 24 of 25 Rev. 25

ALL ACTIVE ON-THE-SPOT CHANGES MUST BE ATTACHED FOR FIELD USE 20020801 Si.OP-SO.WG-0009(Q)

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.

Signature: Date:

(OS/CRS)

Salem 1 Page 25 of 25 Rev. 25

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

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (G-ESG-1)

TASK NUMBER: 1240020502 JPM NUMBER: GOLF NRC - SROA.4 (ESG-1)

ALTERNATE PATH: K/A NUMBER: 2.4.38 IMPORTANCE FACTOR: N/A 4.0 APPLICABILITY: RO SRO EO = RO = STA =- SRO E-I 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 TRAINING SUPERVISOR OPERATIONS MANAGER REPRESENTATIVE 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:

ACTUAL TIME CRITICAL COMPLETION:

JPM PERFORMED BY: GRADE: D SAT r] UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Nuclear Common Page I of 5 Rev. 0

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)

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.

Nuclear Common Page 2 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 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

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

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE 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)

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 Attachment 2 3 Fills out Section A of the Attachment

Unit: 2

EAL#(s): 3.2.2.b

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 NAME:

JOB PERFORMANCE MEASURE 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

5 Complete the ICMF Fills out Section II:

o *Checks block for the emergency CUE: For purposes of the examination, if classification a release occurred during the event then

Time: Current Time check the "radiological release in progress" block. The OS would have

Date: Today's Date checked that block if the ECG had been

EAL#(s): 3.2.2.b done in real time. * *Description of Event: Brief description capturing the major elements KEYATTACHED 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" Nuclear Common Page 4 of 5 Rev. 0

ECG

- -/ ATT2 Pg. 1 of 2 ATTACHMENT 2 ALERT

1. EMERGENCY COORDINATOR (EC) LOG SHEET

"- Initials A. DECLARE AN ALERT AT SALEM UNIT EAL #3 =.4-

Declared at C E*'V**9t rlm hrs on /4,4ý' ____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 CM 1 to implement ECG Attachment 6.

EC

4. DIRECT the Secondary Communicator (CM2) to implement ECG Attachment 8 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 SGS Rev. 03

K ECG ATT 2 ply Pg. 2 of 2 INITIAL CONTACT MESSAGE FORM I. THIS IS COMMUNICATOR IN THE 0 CONTROL ROOM (NAME) El TSC AT THE SALEM NUCLEAR GENERATING STATION, UNIT NO.

II.

9/1* THIS IS NOTIFICATION OF AN AVERT WHICH WAS DECLARED AT '/e/l'exl-/" ON /Qo1 4y(.ATE)47C (Time - 24 HR CLOCK) (DATE)

EAL # -3,-. eo DESCRIPTION OF EVENT: X4/e61 A'*,A(

/, (9C14I /<

1< /1? 0

/4) /4 14, 11Z,4 4 ldzýaz-r 0,-,-

ill. / }

NO RADIOLOGICAL RELEASE IS IN PROGRESS. see NOTE for release 0 THERE IS A RADIOLOGICAL RELEASE IN PROGRESS. definition IV. 33 FT. LEVEL WIND DIRECTION (From): c4,5-20 WIND SPEED: /.2.

(From MET Computer) (DEGREES) (MPH)

V. NO PROTECTIVE ACTIONS ARE RECOMMENDED AT THIS TIME 16..5 EC Initials (Approval to Transmit ICMF)

NOTE:

Radiological Release is defined as: Plant Effluent > Tech Spec Limit of 2.42E+05 pCi/sec Noble Gas or 2.1E+O1 p Ci/sec 1-131.

SGS Rev. 03

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

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (G-ESG-2)

TASK NUMBER: 1240020502 JPM NUMBER: GOLF NRC - SROA.4 (ESG-2)

ALTERNATE PATH: r KIA NUMBER: 2.4.38 IMPORTANCE FACTOR: N/A 4.0 APPLICABILITY: RO SRO EO = RO = STA = SRO LZ 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 TRAINING SUPERVISOR OPERATIONS MANAGER REPRESENTATIVE 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:

ACTUAL TIME CRITICAL COMPLETION:

JPM PERFORMED BY: GRADE: D SAT rD] UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Nuclear Common Page I of 5 Rev. 0

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)

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.

Nuclear Common Page 2 of 5 Rev. 0

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

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE 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) 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 Attachment 2 3 Fills out Section A of the Attachment

Unit:2

EAL#(s): 3.2.3.a

Time: Current Time

Date: Today's Date

Initials as EC Nuclear Common Page 3 of 5 Rev. 0

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

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE 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) S/U evaluation) 4 Call communicators to the Control Room Pages communicators CUE: I am the Primary Communicator

5 Complete the ICMF Fills out Section I1:

*Checks block for the emergency CUE: For purposes of the examination, if classification a release occurred during the event then

Time: Current Time check the "radiological release in progress" block. The OS would have

Date: Today's Date checked that block if the ECG had been 0 EAL#(s): 3.2.3.a done in real time. * *Description of Event: Brief description capturing the major elements KEYATTACHED 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" Nuclear Common 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 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 2 2 Pg. 1 of 2 ATTACHMENT 2 ALERT I. EMERGENCY COORDINATOR (EC) LOG SHEET Initials A. DECLARE AN ALERT AT SALEM UNIT ,

EAL # 0Z- ,-.A3 Declared atJ i/ / hrs on "

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 CMl to implement ECG Attachment 6.

EC

4. DIRECT the Secondary Communicator (CM2) to implement ECG Attachment 8 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 SGS Rev. 03

ECG ATT 2 Pg. 2 of 2 INITIAL CONTACT MESSAGE FORM I. THIS IS COMMUNICATOR IN THE 0l CONTROL ROOM (NAME) El TSC AT THE SALEM NUCLEAR GENERATING STATION, UNIT NO. c___

II.

THIS IS NOTIFICATION OF AN ALERT WHICH WAS DECLARED AT C11/RC0JT", ON A9 (Time - 24 HR CLOCK) (DATE)

EAL # Z. '3. - A, DESCRIPTION OF EVENT:

> 17,2' iAjo X ý57,exw froe6 4;15 6Z c NO RADIOLOGICAL RELEASE IS IN PROGRESS. } see NOTE for release El 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 64,t/j9/oAT EC Initials (Approval to Transmit ICMF)

NOTE:

Radiological Release is defined as: Plant Effluent > Tech Spec Limit of 2.42E+05 pCi/sec Noble Gas or 2.1E+O1 pCi/sec 1-131.

SGS Rev. 03

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

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (G-ESG-3)

TASK NUMBER: 1240020502 JPM NUMBER: GOLF NRC - SROA.4 (ESG-3)

ALTERNATE PATH: K/A NUMBER: 2.4.38 IMPORTANCE FACTOR: N/A 4.0 APPLICABILITY: RO SRO EO = RO = STA = SRO I--

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 TRAINING SUPERVISOR OPERATIONS MANAGER REPRESENTATIVE 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:

ACTUAL TIME CRITICAL COMPLETION:

JPM PERFORMED BY: GRADE: r- SAT UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

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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-3)

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.

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

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (G-ESG-3)

STEP COMMENTS

STEP

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 Attachment 2 3 Fills out Section A of the Attachment = Unit: 2

EAL#(s): 3.2.1.a

Time: Current Time

Date: Today's Date

Initials as EC Nuclear Common Page 3 of 5 Rev. 0

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

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (G-ESG-3)

I I STEP COMMENTS EVAL (Required for UNSAT STANDARD S/u evaluation)

Call communicators to the Control Room Pages communicators CUE: I am the Primary Communicator 5 Complete the ICMF Fills out Section II:

"* *Checks block for the emergency classification CUE: For purposes of the examination, if a release occurred during the event then "* Time: Current Time check the "radiological release in "* Date: Today's Date progress" block. The OS would have checked that block if the ECG had been "* EAL#(s): 3.2.1.a done in real time. "* *Description of Event: Brief description capturing the major elements KEY ATTACHED 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 IOME to the Primary Provides ICMF to CMI within 15 minutes of Communicator (CMI) and direct the CMI 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 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 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 2

,4; 6ir*6-3 Pg. 1 of 2 1,1q ATTACHMENT 2 ALERT I. EMERGENCY COORDINATOR (EC) LOG SHEET Initials A. DECLARE AN ALERT AT SALEM UNIT EAL # S,, c2,, /.. Declared a*/fe-- hrs on 16,46/rk 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 CMl to implement ECG Attachment 6.

EC

4. DIRECT the Secondary Communicator (CM2) to implement ECG Attachment 8 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 SGS Rev. 03

ECG 6 -3 ATT 2 Pg. 2 of 2 Cý INITIAL CC)NTACT MESSAGE FORM I. THIS IS COMMUNICATOR IN THE 0 CONTROL ROOM (NAME) C] TSC AT THE SALEM NUCLEAR GENERATING STATION, UNIT NO.

II. - - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - - - - - - - -

THIS IS NOTIFICATION OF AN ALERT WHICH WAS DECLARED ATr,41/?1,/T- /?/,4 ON l9,,4 V- 4476 (Time - 24 HR CLOCK) "f /(DATE)

EAL # W/A c5, DESCRIPTION OF EVENT: 1/,4' ,A/K /I-.P Q2 2 /4/,

0' NO RADIOLOGICAL RELEASE IS IN PROGRESS. see NOTE for release E0 THERE IS A RADIOLOGICAL RELEASE IN PROGRESS. definition IV.

33 FT. LEVEL WIND DIRECTION (From): c626,. WIND SPEED: _,___2_

(From MET Computer) (DEGREES) (MPH)

V. NO PROTECTIVE ACTIONS ARE RECOMMENDED AT THIS TIME

-'A/f fI4/:-5 EC Initials (Approval to Transmit ICMF)

NOTE:

Radiological Release is defined as: Plant Effluent > Tech Spec Limit of 2.42E+05 jtCi/sec Noble Gas or 2.1E+O I tCi/sec 1-131.

SGS Rev. 03

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

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (G-ESG-SPARE)

TASK NUMBER: 1240020502 JPM NUMBER: GOLF NRC - SROA.4 (ESG-SPARE)

ALTERNATE PATH: r K/A NUMBER: 2.4.38 IMPORTANCE FACTOR: N/A 4.0 APPLICABILITY: RO SRO EO = RO = STA = SRO I--*

EVALUATION SETTINGIMETHOD: Simulate (Simulator or Classroom)

REFERENCES:

Salem ECG TOOLS AND EQUIPMENT: Inform SimulatorOperators- 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 TRAINING SUPERVISOR OPERATIONS MANAGER REPRESENTATIVE 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:

ACTUAL TIME CRITICAL COMPLETION:

JPM PERFORMED BY: GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

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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)

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.

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

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (G-ESG-SPARE)

STEP COMMENTS

STEP

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 Attachment 2 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 Rev. 0 Nuclear Common Page 3 of 5

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

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE 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) 4 Call communicators to the Control Room Pages communicators CUE: I am the Primary Communicator

5 Complete the ICMF Fills out Section I1:

*Checks block for the emergency CUE: For purposes of the examination, if classification a release occurred during the event then

Time: Current Time check the "radiological release in progress" block. The OS would have

Date: Today's Date checked that block if the ECG had been 0 EAL#(s): 3.2.2.a done in real time. - *Description of Event: Brief description capturing the major elements KEYATTACHED 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" Nuclear Common 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 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 jTT 2 Pg. 2 of 2 4f/ INITIAL CONTACT MESSAGE FORM I. THIS IS COMMUNICATOR IN THE 03 CONTROL ROOM (NAME) [] TSC AT THE SALEM NUCLEAR GENERATING STATION, UNIT NO. 42Z-THIS IS NOTIFICATION OF AN ALERT WHICH WAS DECLARED AT_ _______-O___4 (Time - 24 HR CLOCK) (DATE)

EAL # 3.,9. J. 4-. DESCRIPTION OF EVENT:

> / 7 1' III.-r NO RADIOLOGICAL RELEASE IS IN PROGRESS. see NOTE for release C THERE IS A RADIOLOGICAL RELEASE IN PROGRESS . Idefinition IV.

33 FT. LEVEL WIND DIRECTION (From): V/< WIND SPEED:

(From MET Computer) (DEGREES) (MPH)

V. NO PROTECTIVE ACTIONS ARE RECOMMENDED AT THIS TIME a ,)01A7-6".5 ý /r/10-14-S EC Initials (Approval to Transmit ICMF)

NOTE:

Radiological Release is defined as: Plant Effluent > Tech Spec Limit of 2.42E+05 pCi/sec Noble Gas or 2.1E+O1 tCi/sec 1-13 1.

SGS Rev. 03

ECG ATT 2 Pg. I of 2 ATTACHMENT 2 ALERT I. EMERGENCY COORDINATOR (EC) LOG SHEET Initials A. DECLARE AN ALERT AT SALEM UNIT _

EAL # 3, o2 . t Declared atc/2RcA'4r on__e__ _hrs time ate 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 (CM 1) and DIRECT the CM1 to implement ECG Attachment 6.

EC

4. DIRECT the Secondary Communicator (CM2) to implement ECG Attachment 8 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 SGS Rev. 03

ML023290590

Text

REFERENCES:

SUMMARY

7.0 REFERENCES

7.0 REFERENCES

References:

7.1.2 Procedures

7.2 Commitments

1.0 COMMENTS

2.0 SIGNATURES

SUMMARY

7.0 REFERENCES

7.0 REFERENCES

References:

7.1.2 Procedures

7.2 Commitments

1.0 COMMENTS

2.0 SIGNATURES

REFERENCES:

RESPONSE

REFERENCE:

RESPONSE

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REFERENCES:

SUMMARY

SUMMARY

1.0 COMMENTS

2.0 SIGNATURES

1.0 REFERENCES

REFERENCES:

RESPONSE

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RESPONSE

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RESPONSE

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RESPONSE

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SUMMARY

7.0 REFERENCES

4.3 Procedure(s)

7.0 REFERENCES

7.2 Drawings

7.3 Procedures

7.4 Others

References:

7.5.2 Procedures

7.6 Commitments

1.0 COMMENTS

2.0 SIGNATURES

SUMMARY

7.0 REFERENCES

7.0 REFERENCES

7.5 Others

References:

7.6.2 Procedures

7.7 Commitments

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SUMMARY

SUMMARY

SUMMARY

7.0 REFERENCES

7.0 REFERENCES

7.3 Procedures

7.4 Drawings

7.5 Others

References:

7.6.3 Others

7.6.4 Procedures

7.7 Commitments

3.1 Instrumentation