ML022390470

Draft - Section a Operating

ML022390470
Person / Time
Site:	Calvert Cliffs
Issue date:	07/11/2002
From:	Hornick J Constellation Nuclear
To:	Conte R NRC/RGN-I/DRS/OSB
References
50-317/02301, 50-318/02301, NO-1-200
Download: ML022390470 (126)

Text

CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE NO-1-200(NEW)

TASK:

Complete the Shift Staffing Attachment of NO-1-200 PURPOSE:

Evaluates an Operator's Ability to Comply with Shift Staffing Fitness for Duty and Work Hour Limits Requirements JOB PERFORMANCE MEASURE CALVERT CLIFFS NUCLEAR POWER PLANT LICENSED OPERATOR TRAINING Rev. 1

Page 2 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE NO-1-200 (NEW)

TASK:

PERFORMER'S NAME:

Complete the Shift Staffing Attachment of NO-1-200 APPLICABILITY:

RO and SRO PREREQUISITES:

Completion of the knowledge requirement of the Initial License class training programfor Administrative Procedures.

EVALUATION LOCATION:

PLANT SIMULATOR CONTROL ROOM EVALUATION METHOD:

ACTUAL PERFORMANCE ESTIMATED TIME ACTUAL TIME TO COMPLETE JPM:

TO COMPLETE JPM:

DEMONSTRATE PERFORMANCE TIME CRITICAL TASK:

10 MINUTES TASK LEVEL:

TRAIN TOOLS AND EQUIPMENT:

None REFERENCE PROCEDURE(S):

MINUTES NO NO-1-200 SE-1-100 SE-1-101 TASK STANDARDS:

This JPM is complete when Attachment 1 has been completed..

Page 3 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE NO-1-200 (NEW)

TASK:

Complete the Shift Staffing Attachment of NO-1-200 DIRECTIONS TO EVALUATOR:

1.

Read the "Directions to Trainee" to the trainee.

2.

Note the time that the task is started. As the task proceeds, indicate completion of each element using the Standard criteria and the following notation:

"S" for satisfactory completion

- "U" for unsatisfactory completion

- "N" if not observed OR not verifiable Critical elements must be observed or the evaluation is invalid.

3.

When the Terminating Cue is reached, tell the trainee that no further actions are necessary. Note the completion time.

4.

Document any instances of failure to comply with industrial safety practices, radiation safety practices and use of event free tools in the Notes area.

Immediately correct any actions that could result in violation of a safety procedures or personnel injury. NOTE: Violation of safety procedures will result in failure of the JPM.

5.

Questions to clarify actions taken should be asked after completion of the task.

6.

Indicate whether the task was completed satisfactorily on the basis of correct performance of all critical elements and completion of the task within the Estimated Time to Complete for Time Critical tasks.

7.

This JPM contains the steps, notes, cautions, and standards that are applicable to the initial conditions specified in this JPM. Steps that do not directly relate to this JPM, but appear in the procedure, are not listed here. It is the responsibility of the evaluator and/or observer to become familiar with the procedure prior to use of this JPM.

Page 4 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE NO-1-200 (NEW)

TASK:

Complete the Shift Staffing Attachment of NO-1-200

8.

Document any instances of when the near miss threshold was reached due to inappropriate personnel actions/inactions or procedural quality as a result of the following:

Reactivity Management Unplanned power changes > 1%

Reduction of boron concentration of > 5% delta rho Radiation Safety Preventable PCIs Personnel Safety Operations near miss accident Reactor Safety Automatic trip near miss

• Actions required by operators to prevent an automatic trip

• Valid RPS trip or pre-trip alarms due to a plant transient Configuration Control Valve mispositioning or loss of control of tagging boundary resulting in loss of system inventory

Page 5 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE NO-1-200 (NEW)

TASK:

Complete the Shift Staffing Attachment of NO-1-200 JPM STANDARDS (List of minimum Standard Practices for common evolutions at CCNPP)

If non-emergency condition, dispatches a PO to verify pump is ready to be started.

Identify the Control Switch and Indicating Lights, using authorized identification.

Operate the Control Switch, to START, and check expected Indicating Light response.

Check proper pump operation (as applicable):

Motor amps Pump discharge pressure System flow Activation/Clearing of applicable Annunciators (e.g.; Hi Disch Press, Lo Hdr Press) 2,0.

S..p........)

Identify the Control Switch and Indicating Lights, using authorized identification.

Operate the Control Switch, to STOP, and check expected Indicating Light response.

g

-- g B

g a Ch.kexecedsyte 1rspns

(.g.; flo,.pessre level)..

Identify the Control Switch and Indicating Lights, using authorized identification.

Select the Control Switch to the desired position.

Check Valve/Breaker position, using position Indicating Lights.

Check expected system response (e.g.; flow, pressure, level, volts, amps, KW)

Identify the Valve/Breaker Indicating Lights, using authorized identification.

Check the Valve/Breaker is in the correct position.

If Valve/Breaker is not in correct position, report Valve/Breaker position to CRS.

B s

B~I p

s sss s im s

.s.g.......-a sss s~~s Identify the Valve/Breaker Indicating Lights, using authorized identification.

Check the Valve/Breaker is in the correct position.

If Valve/Breaker is not in correct position, operates Valve/Breaker to correct position.

Verify the following:

Suction Valve open Discharge Valve position (as applicable)

Miniflow Valve position (as applicable)

Pump and Motor oil levels are normal Adequate Suction Pressure Identify the Control Switch and Indicating Lights, using authorized identification.

Operate the Control Switch, to START, and check expected Indicating Light response.

Page 6 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE NO-1-200 (NEW)

TASK:

Complete the Shift Staffing Attachment of NO-1-200 Check for proper Pump operation (as applicable):

Smooth, quiet operation consistent with pump history Oil level remains good Proper seal leakoff Proper discharge pressure Expected system flow i

3.1 55I.

7,vLc lly stop Paga I unp i~i i~M a..... -..

5 5*,.

i 5 5

25.am p 5 1-111

.,5, i 52 5n5-5 Identify the Control Switch and Indicating Lights, using authorized identification.

Operate the Control Switch, to STOP, and check expected Indicating Light response.

Check expected system response (e.g.; flow, pressure, level).

Identify the Valve, using authorized identification.

Operate the Valve and check expected position indication change (e.g.; stem rise, pointer).

Check expected System response (e.g.; fluid flow sounds, pressure changes, tank levels).

Identify the Control Switch and Indicating Lights (if applicable), using authorized identification.

Operate the Control Switch and check expected Indicating Light response.

Check expected System response (e.g.; flow, pressure, levels, volts, amps).

• a e

222 2>2222222h.-,

Identify the Valve/Breaker, using authorized identification.

Check the Valve/Breaker is in the correct position, using appropriate position indication (e.g.;

pointer, stem rise, flags, indicating lights).

If Valve/Breaker is not in correct position, report Valve/Breaker position to Control Room.

Identify the Valve/Breaker, using authorized identification.

Check the Valve/Breaker is in the correct position, using appropriate position indication (e.g.;

pointer, stem rise, flags, indicating lights).

If Valve/Breaker is not in correct position, operates Valve/Breaker to correct position.

Page 7 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE NO-1-200 (NEW)

ELEMENT

(* = CRITICAL STEP)

STANDARD TIME START CUE: Provide operator with a filled out copy of NO-1-200 Attachment 1 and an Operations' schedule.

Locate NO-1-200, Section 5. 1.

Same as element.

Determines that an STA from Section 2 needs to be called in Same as element NOTE TO EVALUATOR:

Candidate may reference SE-i-101 to check work hour limits.

CUE: Scott Henry is available, Fit for Duty, and has not consumed alcohol.

I

"""No NAs indicated on included attachments TIME STOP TERMINATING CUE:

This [PM is complete when NO-1-200 Attachment 1 and SE-1-100 forms are completed. No further actions are required.

Page 8 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE NO-1-200 (NEW)

TASK:

Complete the Shift Staffing Attachment of NO-1-200 Document below any instances of failure to comply with industrial safety practices, radiation safety practices and use of event free tools. NOTE: Violation of safety procedures will result in failure of the JPM.

NOTES:

DID A NEAR MISS OCCUR DUE TO INAPPROPRIATE PERSONNEL ACTIONS/INACTIONS OR PROCEDURAL QUALITY?

YES (If yes, provide comments below)

NO COMMENTS:

The operator's performance was evaluated against the standards contained in this JPM and determined to be SATISFACTORY UNSATISFACTORY EVALUATOR'S SIGNATURE:

DATE:

CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE DIRECTIONS TO TRAINEE:

I To complete the task successfully, you must:

• perform each critical element correctly. You must inform the evaluator of the indications you are monitoring. Where necessary, consider the evaluator to be the CRS.

• comply with industrial safety practices, radiation safety practices and use of event free tools. NOTE: Violation of safety procedures will result in failure of the JPM.

2.

Initial Conditions:

a.

Units 1 and 2 are at 100% power.

b.

You are performing the duties of the oncoming SM (Section 1) for Monday, July 15.

c.

The PPO informs you that Dave Fiore is on vacation and Mike Fick has called in sick.

d.

Scheduled workload requires that deviation from the minimum staffing requirements is not warranted.

e.

The Training crew is on a benchmarking trip to Nine Mile Point.

3.

Initiating Cue: Given the Operations' schedule, you are to complete the attached NO-1-200 Shift Staffing Attachment and all other attachments of other administrative procedures as required. Are there any questions?

You may begin.

NO-1-200 Control of Shift Activities Revision 23 Page 61 of 86 ATTACHMENT 1, SHIFT STAFFING WHEN BOTH UNITS ARE OPERATING IN MODES 1 THROUGH 4 [B0516]

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NAME qCt uu-C610'

% S R

%&R PC7 PI WATCHSTATION ASSIGNMENT SM CRS(U1/U2)

PWS(U1U2)

STA CRO-I RO-I CRO-2 RO-2 PPO OSO TBO-I TBO-2 ABO-I ABO-2 FASW FASR FBM FBM FBM SRST SCT EMERG COMM EXTRA EXTRA I

NAME l

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SAFE SHUTDOWN ASSIGNMENT SM CRS(Ul2)

N/A OTA STA CRO-4 RO-I CRO-2 RO-2 N/A OSO TBO-1 TBO-2 ABO-1 ABO-2 FASW FASR FBM FBM FBM N/A N/A N/A CONTROL ROOM EVACUATION REPORTING AREA Ul 45'SWITCHGEAR ROOM*

45' SWITCHGEAR ROOM l

N/A FIRE BRIGADE LOCKER*

U-I 45' SWITCHGEAR ROOM*

U-I 45'SWITCHGEAR ROOM U-l 45' SWITCHGEAR ROOM U-2 45'SWITCHGEAR ROOM U-2 45' SWITCHGEAR ROOM N/A U-2 45' SWITCHGEAR ROOM U-I 45'SWITCHGEAR ROOM U-2 45' SWITCHGEAR ROOM U-I 45' SWITCHGEAR ROOM IU-2 45' SWITCHGEAR ROOM FIRE BRIGADE LOCKER FIRE BRIGADE LOCKER FIRE BRIGADE LOCKER FIRE BRIGADE LOCKER FIRE BRIGADE LOCKER N/A N/A N/A I1 2

l l

I The STA can not be the SM or the OTA. The CRS shall report to U-2 45' SWGR Rm unless acting as the STA, in which case another SRO shall be designated. If 2 CRS' are stationed, one should report to each 45' SWGR Rm. If only 3 SRO's are on shift, one RO shall be assigned the OTA duties. An additional TBO qualified person shall be designated to perform the RO duties for AOP-9, except for tripping the reactor.

Staffing requirements have been met per Section 5.1.A.

MINIMUM SHIFT STAFFING HAS BEEN MET

)

SM/CRS DATE SHIFT INITIAL FORWARD TO OPERATIONS SHIFT SENIOR ADMINISTRATIVE ASSISTANT FOR RETENTION

Nuclear Plant Operations 2002 Schedule Rev. 02/26/02 M T W

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Dec/Jan 17 18 1 9 20 21 22 2326 7 28 29 30 31 2

3 4

5 6

7 8

9 10 11 12 13 14 15 16 17 18 19 2

Jan/Febl 2223 24 25 26 27..28 29 30 31lFeb 2 3

4 5

6 7

8 9 10 1112 1314 15 Feb/Mar May/Jun 6

7 8

9 10 1 1 1 2 1 3 14 15 1 6 1 7 1 8 1 9 2021 22 23 24 25 26 28 29 3031 Jun 2

3 4

5 6

7 8

9 Jun/Jul 1 0 11 12 1 3 14 1 5 1 6 1 7 18 19 20 21 22 23 2

25 26 27 28 29 30Ju 2

3 5

6 7

8 9 1 0 1 1 1 2 1 3 1

4 Jul/Aug 1 5 1 6 17 1 8 19 20 2 1 22 2324 25 26 27 28 2930 31 Aug 2 3

4 5

6 7

8 9 1 0 1 1 1 2 1 3 1 4 1 5 1 6 1 7 1 8 ug/Sep 1 9 20 21 22 23 24 25 26 2728 29 30 31 Sep 3

4 5

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10 11 12 13 14 15 16 17 18 19 20 21 22 23 262 28 2

03 Note: Scheduled training weeks with a holiday= all training days with no relief day.

Seton2-._M;>

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~J Candidate Lynch Frye Grooms Shick NOS TRAINING NPAD McCord Hornick (*)

O'Meara Urnphrey Korsnick Getz Morgan ()Martin, B.

Mleerbach ()

Hayden (*)

Fick (*)

Hubbard Love ()Gaines

()Geneva

()Barger Drown Fiore Henry ()Allor

()Suter Beavers ()Bleacher Riti (*)

Huber Naley Gunter Hummer Montana Reichard LICENSE CLASS Ford Drumngoole Douglas Fleegle Hogg Gambill Penn Furfaro Lyson Cvetkovic McLaughlin Lofton WK COORD McHale Smith Gretz Heiska Gilligan Sloan Miller, S.

Pace Davis, R.

Triplett Robertson Supanich Kahl Solomon Austin, JI(*)

Henderson Nehf Tupik Kelly King Bazyk Fleshman Carey McNeil Darrow Barton Hammans Jones, C.

Boggs.-

Fredge Burger Shobert Jones, R.A.

Leturno Baldwin Lewis Quade Carroll VanDerSnick

.Linehan Taylor, E.

Hailer Eide Papier Sheran Ficke Bald Williams, J.M.

Martz York Etnoyer Wroten Buckler Lankford Jarrett Blue PROD. SUPT.

Kettler Cowan Martin, J.

Mattingly Colgain Gioffre NO Klecha Joy Martinez Rulley Huse Watson Macklin

• Ridgelly Rickards Nukolczak Sharpe Sullick FIN TEAM Stanley, D.

Wall McPherson Truslow

-Taubert Jones (*)

SIFTY SVCS Whitfield Woods Buckmaster Bussler Hailer Baldwin York Steffe (Nehf)

Etnoyer (McHale)

(Penn)

Eide OUTAGE PLT ENGRG (Triplett)

(Gambill)

(Davis, R.)

(Smith)

(Henderson) floffman (*)

Dean (*)

Shift Mngrs & Supervisors

(*) =STA Shift Manager Alternate

(*) = STA Senior Reactor Operators Control Room Operators

(*)

=STA Principal Plant Operators Nuclear Plant Operators g:\\ccnppd\\npo\\report\\ccweb~xs-file\\2002npoa.xis

Fitness For Duty Program SE-1-100 Revision 9 Page 40 of 40 ATTACHMENT 5, CALL-IN REPORTING CHECKLIST Individual's Name:

Date:

ITimne Notified:

Monthly or Weekly Employee?

(Check One)

D Monthly D Weekly Supervisor:

IeotTime:

NOTE: If report time is going to be greater than five hours after notification, the Fitness for Duty Inquiry section is not required to be completed. Forward all forms to Fitness for Duty Program Administrator, Dept. 47, CCNPP, 2nd Floor, OTF.

FITNESS FOR DUTY INQUIRY A.

Are you Fit for Duty?

L Yes El No If NO, advise the individual not to report to work.

B.

Have you consumed any alcohol within the last five (5) hours?

LI Yes Mi No If YES, it is recommended that an individual who consumes alcohol within the five hour period not be requested to report to work. However, if an individual is required, he/she must report to the Nuclear Security Shift Supervisor for a breathalyzer test prior to reporting to work.

ASSESSMENT OF FITNESS FOR DUTY Based on the telephone inquiry, the individual is:

LI Fit for Duty EL Fit for Duty pending breathalyzer results R Not Fit for Duty Reminder: Are the requirement of SE-1-101, Work Hour Limits, applicable to this call-in?

Signature (individual making the call)

Print Name Note: Forward to the Fitness for Duty Program Administrator, Dept. 47, CCNPP, 2nd Floor, OTF, if the individual reports to work as a result of this call-in. If the individual does not report to work as a result of this call-in, the form may be destroyed.

Control of Shift Activities NO-1-200 Revision 23 Page 15 of 86 5.0 PROCESS 5.1 Shift Complement and Functions [B04591 A.

Minimum Staffing Requirements: Shift staffing shall be according to the following table

[B05161 [B05251 [B04631:

NOTE In the following table, RO refers to a licensed operator as defined in NO-1-100, Conduct of Operations.

Both units operating One Unit Mode 1-4 Both Units Modes in Modes 1-4 One Unit Mode 5, 6, or defueled 5, 6, or defueled SRO 3

3 2

STA 1

1 0

RO 4

3 3

ABO 2

1 1

TBO 2

1 I

OSO 1

1 1

SRST 1

I I

SCT I

I I

FASR 1

I I

FASW I

I I

OTA I

1 1

FBM 3

3 3

Total Licensed Operators 7

6 5

(minimum)

Total Shift Personnel 20 17 16 (minimum)

1.

The Shift Manager/CRS shall use Attachments 1 - 4 to document the specific assignments for the above watchstations as well as the safe shutdown and Control Room evacuation assignments.

2.

The Shift Manager shall ensure that the above manning levels are met. The Shift Manager has the authority to require the service of any Company employee as necessary to support safe operation of the plant.

3.

The Shift Manager has the authority to deviate from the shift complement provided the minimum manning and license requirements of the Technical Specifications are met.

4.

Overtime requirements shall be according to SE-l- 1 01, Use of Overtime.

5.

The Shift Manager may authorize one ABO to cover both ABO watches or one TBO to cover both TBO watches if necessary, provided the individual is properly qualified on both watchstations. 1B0522J

a.

This does not relax the staff requirements for safe shutdown for 2 TBOs and 2 ABOs.

NO-1-200 Control of Shift Activities Revision 23 Page 16 of 86 5.1 Shift Complement and Functions 1B04591 (Continued)

6.

If the RO is assigned to the OTA position, an additional TBO qualified person is required for safe shutdown. This person shall perform the RO safe shutdown duties with the exception of tripping the reactor.

a.

In this case, the CRO shall assume responsibility for tripping the reactor.

7.

The STA shall not fill the position of the OTA. tB05231

8.

The assigned STA shall not be concurrently assigned the duties of the CRO or RO.

[B05381

9.

The assigned STA shall not be one of the required SRO's except under unusual conditions and only when authorized by the GS-NPO or Shift Manager per step 5.1.A.3.

10.

OTA, FASW, FASR and FBM personnel shall be in addition to those required for safe shutdown. 1B04631

a.

The OTA may be one of the required SRO's or RO's.

b.

Typically, the FASW is the Fire Brigade Leader and the FASR and 3 other Plant Operators man the Fire Brigade. However, personnel from other work groups may fulfill the role of Fire Brigade member as long as they clearly have no assignments that conflict with their ability to respond in a safe shutdown scenario.

B.

Additional Staffing Requirements I1.

During Core Alterations: 1B05251 An SRO shall be designated the Fuel Handling Supervisor (FHS).

a.

The FHS shall directly supervise the alterations from the Containment 69 foot elevation and have no other concurrent duties. The FHS is in addition to the requirements of 5.1.A and shall:

(1)

Maintain an overview of the fuel handling process within the Containment, and not act as an equipment operator.

(2)

Ensure that all applicable requirements of Technical Specifications 3.9 and TRM 15.9 are met (using the applicable portions of OP-5 Mode 6 checklist) for the evolution in progress and that all activities are performed in a safe manner.

(3)

Direct implementation of appropriate AOPs for dropped or damaged fuel assemblies, abnormally rising count rates (or loss of audible indication), sudden reductions in refueling pool or spent fuel pool levels, or loss of communications with the Control Room.

NO-1-200 Control of Shift Activities Revision 23 Page 17 of 86 5.1 Shift Complement and Functions 1B04591 (Continued)

b.

When inserting or withdrawing fuel assemblies from the core, the Refueling Machine Operator shall be a licensed operator, an individual in training for a license, or a properly trained contractor.

(1)

If an individual in training for a license or a contractor is used, the FHS shall be on the Refueling Machine during such core alterations.

(2)

The Refueling Machine Operator, if a licensed operator, shall be in addition to the minimum staffing requirements of this procedure.

c.

A licensed operator shall be designated the Refueling Control Room Operator (RCRO).

The RCRO shall:

(1)

Coordinate the movement of fuel assemblies/CEAs during core alterations.

(2)

Be in direct communication with personnel operating the refueling equipment and shall monitor for reactivity changes in the Control Room.

(3)

Be in addition to the minimum staffing requirements of this procedure.

(4)

Maintain the Refueling Status Board and document any fuel handling problems.

C.

Control Room Watch Coverage I1.

General Guidelines:

a.

The Shift Manager shall make all decisions regarding assignment of CRS's based on shift manning requirements, plant conditions and according to 5.2.B. I.

b.

Each CRS shall report to the Shift Manager.

c.

The Shift Manager shall not use call-ins or scheduled overtime to obtain a CRS for each Unit unless necessary based on manning requirements or workload.

d.

The CRS for a Unit shall not concurrently be assigned as a "dedicated SRO". The Shift Manager shall determine whether to relieve a Unit CRS in order to supply the dedicated SRO function.

e.

Each Unit CRS shall complete the turnover process for both Units according to NO-1-207, Nuclear Operations Shift Turnover prior to relieving the assigned watch. This ensures a smooth turnover process when one CRS must leave the Control Room for any reason (meetings, breaks, evolutions such as ESFAS testing, and certain EOP/AOP scenarios, etc.).

NO-1-200 Control of Shift Activities Revision 23 Page 18 of 86 5.1 Shift Complement and Functions [B04591 (Continued)

2.

Control Room Supervisors In order to provide more direct SRO involvement and supervision of evolutions, tests and coordination of maintenance activities, and to provide better equipment status control, the following guidelines are established:

a.

Four SRO's on Shift (in addition to the Shift Manager);

+

When a full complement of SRO's are on shift, a CRS shall be assigned to each Unit. The remaining "extra" SRO may be assigned as the OWC, an additional PWS, SMA, or a "dedicated SRO" as necessary by the Shift Manager.

If more than one "dedicated SRO" is required then the dedicated SRO position shall take precedence over assigning an SRO to each Unit.

b.

Three SRO's on Shift (in addition to the Shift Manager);

If the extra SRO is not required for other work, then an SRO should be assigned to each Unit by the Shift Manager.

3.

CRO/RO To provide continuity for maintenance, testing, and a more accurate status of plant conditions, the CRO/RO combination on each Unit should remain the same throughout the entire shift week.

a.

The Shift Manager shall approve all deviations from this policy.

C.

Shift Fire and Safety Coverage The Fire and Safety shift personnel shall perform assigned responsibilities according to NO-1-100.

1.

Shift Fire and Safety Responder (FASR) shall:

a.

Act as shift first aid person.

b.

Act as shift Confined Space rescue.

c.

Act as Fire Brigade Leader Alternate.

5.2 Turnover and Relief A.

Shift Relief and Watchstation Turnover

1.

Shift relief shall be conducted according to NO-1-207, Nuclear Operations Shift Turnover.

2.

Watchstation turnover shall be conducted according to NO-1-207, except as allowed in 5.2.B of this procedure.

Calvert Cliffs Nuclear P6wer Plant Administrative Procedure WORK HOUR LIMITS FORMERLY "USE OF OVERTIME" SE-1-101 Revision 3 This procedure is EXEMPT from 10CFR50.59/10CFR72.48 Reviews Effective Date Tech Spec Related A 1 Management Related Writer: J. T. Carroll Sponsor: Plant General Manager App rovedl"

• LI

/ -171CIo>,

Manager 6.te

SE-1-101 Work Hour Limits Revision 3 Page 2 of 12 RECORD OF REVISIONS AND CHANGES Revision Change Summary of Revision or Change 3

0 Eliminated Bases [B-21. Staff work hours are controlled by Technical Specifications 5.2.2.e. GL 82-12 is retained as a developmental reference.

Added clarification -7 day period means 168 continuous hours.

Changed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period work hour limit to 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br /> in any 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period.

Added "supporting outage critical path" to list of examples where deviating from work limits may be appropriate.

Deleted requirement that circumstances must be "unforeseen" to allow deviation from work hour limits.

Added requirement for a periodic independent review to ensure that excessive work hours have not been assigned.

Work Hour Limits SE-v1-101 Page 3 of 12 TABLE OF CONTENTS SECTION TITLE PAGE

1.0 INTRODUCTION

5 1.1 Purpose................................

5 1.2 Scope/Applicability...............................

5

2.0 REFERENCES

5 2.1 Developmental...............................

5 2.2 Performance.

5 3.0 DEFINITIONS 4.0 RESPONSIBILITIES...............................

6 5.0 PROCESS 6

5.1 Work Hour Limits.6 5.2 Exceeding Work Hour Limits [B-5]................................

7 5.3 Independent Review...................

9 6.0 BASES 9

7.0 RECORDS 9

ATTACHMENT 1, AUTHORIZATION TO EXCEED WORK HOUR LIMITS.10 ATTACHMENT 2, SECTION 5.2.D DOCUMENTATION REQUIREMENTS APPLICABILITY.........................................................................................

12 I

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Work Hour Limits SE-v1-101 Page 5 of 12

1.0 INTRODUCTION

1.1 Purpose This procedure establishes controls to ensure individuals performing activities at Calvert Cliffs Nuclear Power Plant (CCNPP) are not overly fatigued such that their mental alertness and decision-making ability may be impaired. [B-i]

1.2 Scope/Applicability A.

The work hour limits specified in Section 5.1 of this procedure apply to all personnel working at CCNPP.

B.

The documentation requirements of Section 5.21) apply only to personnel providing direct plant support or performing or supervising field activities that could directly impact personnel safety and the safe and reliable operation of the plant. Attachment 2, Section 5.2.D Documentation Requirements Applicability, provides additional guidance.

2.0 REFERENCES

2.1 Developmental A.

10 CFR 26.20 B.

ANSI N1 8.1-1971, Selection and Training of Nuclear Power Plant Personnel C.

NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours D.

NRC Generic Letter 83-14, Definition of "Key Maintenance Personnel" E.

NUREG-0737,Section I.A.1.3 F.

Technical Specification 5.2.2.e 2.2 Performance A.

QL-2-100, Issue Reporting and Assessment 3.0 DEFINITIONS A.

Office Staff All administrative, management and support groups such as: procedure writers, engineers not directly supervising or performing plant support activities, training staff, planners, schedulers and document control services.

B.

Work Hour Limits Work limits found in Section 5.1.

1

Work Hour Limits SE-1-101 Revision 3 Page 6 of 12 4.0 RESPONSIBILITIES The following individuals and organizations are assigned responsibilities within this procedure:

A.

Plant General Manager.

B.

Department Managers l Project Manager - Steam Generator Project.

C.

Plant Superintendents / General Supervisors / Directors.

D.

Supervisors.

E.

Individuals who work in excess of the limitations stated in Section 5.1.

F.

Fitness for Duty Program Administrator 5.0 PROCESS 5.1 Work Hour Limits NOTE Work hour limits are established to ensure that individuals performing activities that directly impact personnel safety and the safe and reliable operation of the plant are not overly fatigued such that their mental alertness and decision-making ability might be impaired.

A.

Supervisors should develop work schedules so work can be accomplished during scheduled working hours, and, to the maximum extent practical, avoid the use of overtime. However, when circumstances dictate working beyond scheduled working hours, the following limitations apply:

NOTE For criteria in Section 5.1 below, turnover time and travel time between the individual's home and CCNPP should NOT be included.

For purposes of consistency, however, turnover time should typically be no more than one-half hour at the beginning of a shift and one-half hour at the end of a shift and appropriately documented on the individual's time sheet.

B.

An individual should not be permitted to work more than:

1.

16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight.

2.

16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period.

3.

28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br /> in any 48-hour period.

4.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period (168 continuous hours).

C.

There shall be a break in an individual's work schedule of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> following a work period for which work goes beyond the limitations in Section 5.1.B.

SE-1-101 Work Hour Limits Revision 3 Page 7 of 12 5.1 Work Hour Limits (Continued)

D.

The requirements and limits specified in 5. 1.B and C apply to all hours worked if anv portion of an individual's total work time is spent performing or supervising field activities.

Examples:

1.

An individual works 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> in an office environment that is exempt from the documentation requirements of this procedure and then goes to the plant and begins work on an activity that falls under the documentation requirements of this procedure. For purposes of work hour limits and this procedure, as soon as the person begins work in the covered activity, he/she is considered to already have worked 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

2.

An individual works 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> in an office environment that is exempt from the documentation requirements of this procedure and then begins an 8-hour shift on an activity that falls under the documentation requirements of this procedure.

After 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> on the second work activity, the individual has worked 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period and shall be sent home or be evaluated under this procedure and have Attachment 1 approved prior to further work.

3.

An individual works 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> on an activity that falls under the documentation requirements of this procedure and then returns to an office environment that is exempt from the documentation requirements of this procedure to work another 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. That person then leaves the office environment and begins an 8-hour shift in the field. At the beginning of that 8-hour shift, that person is considered to have already worked 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for purposes of the work hour limits of this procedure.

E.

If conditions warrant, supervisors may establish more restrictive limitations than contained in this procedure.

5.2 Exceeding Work Hour Limits [B-51 A.

On rare occasions, circumstances may necessitate allowing personnel to work beyond the limitations established in Section 5.1.

Examples:

Circumstances that may warrant deviating from limitations of Section 5.1 include, but are not limited to: [B-4]

Limiting Conditions for Operations (LCO) Action statements requiring unexpected activities to return equipment important to safety back to service.

Unexpected activities necessary to minimize the time in undesirable configurations or line-ups.

Maintenance on LCO equipment when unexpected or unsatisfactory results are observed.

Supporting outage critical path.

Substituting for a sick employee on short notice.

Weather-related extension of work periods.

I

SE-1-101 Work Hour Limits Revision 3 Page 8 of 12 5.2 Exceeding Work Hour Limits [B-51 (Continued)

B.

Work in excess of the limitations of Section 5.1 shall NOT be routinely authorized. [B-1]

C.

Requirements applicable to all personnel working at Calvert Cliffs

1.

Personnel shall track their work hours and notify their supervisors if they expect to reach the limits of Section 5.1.

2.

Personnel shall obtain approval from their General Supervisor, Manager Direct Report, Project Manager - Steam Generator Project, or Manager prior to exceeding any of the work hour limits and as close to exceeding the limits as practical, except as authorized in Section 5.2.E. Approval shall be given only if the following conditions are met:

a.

The work activity is necessary to support safe and reliable operation of the plant.

AND

b.

Other personnel cannot reasonably be made available to perform the work activity.

3.

Personnel shall generate an Issue Report according to QL-2-100, Issue Reporting and Assessment, if work hour limits were exceeded without obtaining prior approval.

4.

Supervisors shall;

a.

Ensure personnel are fit for duty at all times.

b.

Make more frequent direct observations of personnel exceeding work hour limits.

D.

Additional requirements applicable to personnel providing direct plant support or performing or supervising field activities that could directly impact personnel safety or the safe and reliable operation of the plant. (Refer to Attachment 2, Section 5.2.D, Documentation Requirements Applicability, provides additional guidance.)

1.

Supervisors of personnel who expect to exceed the limitations of Section 5.1 shall complete Attachment 1, Authorization to Exceed Work Hour Limits.

a.

A separate authorization form shall be completed for each activity or evolution.

b.

One authorization form may be used for a group of individuals working the same activity or evolution, e.g., an Operations shift.

2., Authorization to Exceed Work Hour Limits, shall be approved in advance by the responsible General Supervisor, Manager - Direct Report, Project Manager - Steam Generator Project, or Manager.

3.

Supervisors shall retain Attachment 1 until work for which permission was given to exceed the limits has been completed.

4.

Completed Attachment ls shall be forwarded to the Fitness for Duty Program Administrator.

SE-1-101 Work Hour Limits Revision 3 Page 9 of 12 5.2 Exceeding Work Hour Limits [B-51 (Continued)

E.

When the Site Emergency Response Plan is implemented, Center Directors shall:

NOTE Emergency Response Center Directors are NOT required to complete Attachment 1.

1.

Ascertain the status of individuals in their Centers with respect to exceeding work hour limits of Section 5.1.

2.

Verify the ability of those exceeding the limits to continue in their Center function.

3.

Continue to monitor individuals who have exceeded the work hour limits of Section 5.1.

4.

Replace individuals who cannot adequately perform their duties due to fatigue with other qualified individuals.

5.3 Independent Review A.

The fitness for Duty Program Administrator shall perform an annual review to ensure that excessive hours have not been assigned. The results of the review shall be reported to the Plant General Manager. [B-i]

6.0 BASES

[B-1]

Technical Specification 5.2.2.e

[B-3]

QA Audit 90-17-05, Nuclear Operations Overtime Audit AIT # AF9013844

[B-4]

NUMARC Guideline 91-06, Shutdown Safety Section 3.2.5 AIT # 1U9200171, Deletion of distinction between shutdown and operating Overtime limitations.

[B-5]

BGE Response to Notice of Violation CT9300052 Milestone 005 7.0 RECORDS Completed Attachment Is, Authorization to Exceed Work Hour Limits, shall be retained by the Fitness for Duty Program Administrator for one year and then may be discarded.

SE-1-101 Work Hour Limits Revision 3 Page 10 of 12 ATTACHMENT 1, AUTHORIZATION TO EXCEED WORK HOUR LIMITS (Page 1 of 2)

THIS ISA FILLABLE FORM ffor A-D onlyl LOCA TED ON THE CAL VERT CLIFFS FORMS WEB PA GE.

A.

Name of individual for which authorization to exceed work hour limits is requested (If for more than one person, e.g., an entire Operations shift or Nuclear Security shift, complete page 2 of 2 and submit with this form.):

Print Name:

Section/Unit:

[l Check here if form is for multiple individuals and names are listed on page 2.

B.

This form shall be used to authorize an individual or individuals to exceed the following limits:

1. [1 Work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight.

2. Ii Work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in a 24-hour period.

3.

0 Work more than 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br /> in a 48-hour period.

4. El Work more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in a 7-day period (168 continuous hours).

5. E Will have less than an 8-hour break after working in excess of 1 through 4 above.

Check (q1) appropriate boxes for limitations that will be exceeded.

C.

Date/Dates overtime limitations will be exceeded: [B-3] (Multiple dates indicate when an activity cannot be completed in a single day or results in limits being exceeded on subsequent days.)

D.

Justification for exceeding linmitations listed in Section B above.

E.

REQUESTING SUPERVISOR Printed Name and Signature Date F.

APPROVAL. Approval shall be by General Supervisor, Manager - Direct Report, Project Manager - Steam Generator Project, or Manager.

Printed Name and Signature Date G.

OBSERVATIONS NOTE: More frequent observations should be performed for people exceeding work hour limits.

Forward form (including page 2, if applicable), to Fitness for Duty Program Administrator when individual(s) is/are no longer exceeding work hour limits.

Work Hour Limits SE-1-101 Revision 3 Page 11 of 12 ATTACHMENT 1, AUTHORIZATION TO EXCEED WORK HOUR LIMITS (Page 2 of 2) l li I

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SE-1-101 Work Hour Limits Revision 3 Page 12 of 12 ATTACHMENT 2, SECTION 5.2.D DOCUMENTATION REQUIREMENTS APPLICABILITY The documentation requirements of Section 5.2, Exceeding Work Hour Limits, apply only to personnel providing direct plant support or performing or supervising field activities that could directly impact personnel safety and the safe and reliable operation of the plant.

A.

Calvert Cliffs Nuclear Power Plant Department (CCNPPD) [41]

1.

Documentation requirements are applicable to all CCNPPD personnel except office staff.

B.

Nuclear Engineering Department (NED) [42]

1.

Documentation requirements are applicable to personnel performing:

Shift engineering activities associated with fuel handling.

Post-Start-Up Testing.

Fuel management surveillances.

Providing direct support for field activities.

2.

All other NED personnel are exempt from documentation requirements.

C.

Nuclear Performance Assessment Department (NPAD) [43]

Documentation requirements are not applicable to NPAD personnel.

D.

Nuclear Support Services Department (NSSD) [471

1.

Documentation requirements are applicable to personnel performing:

Nuclear Security shift activities.

Receipt Inspections.

2.

All other NSSD personnel are exempt from documentation requirements.

E.

Nuclear Project Management Department (NPMD) [481

1.

Documentation requirements are applicable to personnel performing hands-on work and first line supervisor duties, such as test supervisor.

2.

All other NPMD personnel are exempt from documentation requirements.

F.

Documentation requirements for personnel on temporary assignment to another department or performing work sponsored by a CCNPP department will be according to the requirements for the department sponsoring the work.

Control of Shift Activities N%44 ATTACHMENT 1, SHIFT STAFFING WHEN BOTH THROUGH 4 [BO NO-1-200 Revision 23 Page 61 of 86 ARE OPERATING IN MODES 1

.}

NAME 50 59 LATsP kty-q I A r-T P

WATCHSTATION ASSIGNMENT SM CRS(UI/U2)

PWS(U1IU2)

STA CRO-i RO-I CRO-2 RO-2 PPO OSO TBO-I TBO-2 ABO-I ABO-2 FASW FASR FBM FBM FBM SRST SCT EMERG COMM EXTRA EXTRA N NAME LOAM' T Of /6 t3@

SAFE SHUTDOWN ASSIGNMENT SM (tRS(U1U2)

'N/A STA

_CRO-I t0-I__

CRO-2

_ 0-2 N/A OSO TBO-I TBO-2 ABO-I ABO-2 FASW FASR FBM FBM FBM N/A N/A N/A CONTROL ROOM EVACUATION REPORTING AREA Ul ~

_5SICGA ROM Ul45'SWITCHGEAR ROOM*

N/A FIRE BRIGiADE LOCKER*

U-l 45' SWITCHGEAR

ROOM, U-1I 45'5WITCHGEAR ROOM

_5SICGA ROO U-l 45' SWITCHGEAR ROOM U-2 45' SWITCHGEAR ROOM U-2 4S SWITCHGA ROOM U-l 45' SWITCHGA ROOM U-2 45' SWITCHGA ROOM U-l 45' SWITCHGEAR ROOM U-2 45' SW1ITCHGEAR ROOM FIRE BRIGADE LOCKER I

FIRE BRIGADE LOCKER l

FIREBRIGDE LCKE FIRE BRIGADE LOCKER l

FIRE BRIGADE LOCKER 1

NIA NIA

)

I 11 Ik I ne zi IA can not be the SM or the OTA. The CRS shall report to U-2 45' SWGR Rm unless acting as the STA, in which case another SRO shall be designated. 'If 2 CRS' are stationed, one should report to each 45' SWGR Rm. If only 3 SRO's are on shift, one RO shall be assigned the OTA duties. An additional TBO qualified person shall be designated to perform the RO duties for AOP-9, except for tripping the reactor.

.Staffing requirements have been met per Section 5.1.A.

.)

MINIMUM SHIFT STAFFING HAS BEEN MET SMICRS DATE SHIFT INITIAL FORWARD TO OPERATIONS SHIFT SENIOR ADMINISTRATIVE ASSISTANT FOR RETENTION

Fitness For Duty Program Revi SEi-o0 Page 40 of 40 ATTACHMENT 5, CALL-IN REPORTIN CHECKLIST Individual's Name:

Date:

Time Notified:

Monthly or Weekly Employee?

(Check One)

[rMonthly

1 Weekly Supervisor u

ReportcTime:

NOTE: If report time is going to be greater than five hours after notification, the Fitness for Duty Inquiry section is not required to be completed. Forward all forms to Fitness for Duty Program Administrator, Dept. 47, CCNPP, 2nd Floor, OTF.

FITNESS FOR DUTY INQUIRY A.

AreyouFitforDuty?

NaiYes f No If NO, advise the individual not to report to work.

B.

Have you consumed any alcohol within the last five (5) hours?

R Yes

[>/No If YES, i t

is recomtend ed that an individual who consumes alcohol within the five hour period not be Orequested to report to work. However, if an individual is required, hefshe must report to the Nuclear Security Shift Supervisor for a breathalyzer test prior to reporting to work.

ASSESSMENT OF FITNESS FOR DUTY Based on the telephone inquiry, the individual is:

P'Fit for Duty Fit for Duty pending breathalyzer results D1 Not Fit for Duty Reminder: Are the requirement of SE-1-101, Work Hour Limits, applicable to this call-in?

lgltre (idvdual making the caU)

Print Name Note: Forward to the Fitness for Duty Program Administrator, Dept. 47, CCNPP, 2nd Floor, OTF, if the individual reports to work as a result of this call-in. If the individual does not report to work as a result of this call-in, the form may be destroyed.

I

Calvert Cliffs Nuclear Power Plant ADMIN Al Topics Security Knowledge of facility requirements for controlling vitalcontrolled area access K/A 2.1.13 [2.91 Question a:

A contracted engineer (non-CEG employee) has requested access to the Unit-2 Generator and Unit Protection room.

What requirements must be met to grant him/her unescorted access to this area?

[1 1 ISatisfactory Unsatisfactory Candidate 1 of 4 ADMIN #1 Questions Security Revised 05/30/02

Calvert Cliffs Nuclear Power Plant ADMIN Al Topics Security Knowledge of facility requirements for controlling vital/controlled area access K/A 2.1.13 [2.91 Question a:

A contracted engineer (non-CEG employee) has requested access to the Unit-2 Generator and Unit Protection room.

What requirements must be met to grant him/her unescorted access to this area?

Answer:

The person must be badged for site access by completing GOT and have access rights to the switchgear rooms. To get the key to the Generator and Unit Protection room, the person must also have written permission from an Operations Supervisor.

Reference Use Allowed ? yes

Reference:

GOT, NO-I-110 section 5.1 and attachment 1.

Comments:

m 1Satisfactory Unsatisfactory Candidate 2 of 4 ADMIN #1 Questions Security Revised 05/30/02

Calvert Cliffs Nuclear Power Plant ADMIN Al Topics Security Security-Knowledge of system status criteria which require notification of plant personnel K/A 2.1.14 [3.31 Question b:

On completion of his walk-down the engineer reports that he broke the key off in the door lock.

The door is locked, but a part of the key is still in the lock.

Who should be notified and what actions should be taken?

Satisfactory Ll I Unsatisfactory Candidate 3 of 4 ADMIN #1 Questions Security Revised 05/30/02

Calvert Cliffs Nuclear Power Plant ADMIN Al Topics Security Security-Knowledge of system status criteria which require notification of plant personnel K/A 2.1.14 [3.3]

Question b:

On completion of his walk-down the engineer reports that he broke the key off in the door lock.

The door is locked, but a part of the key is still in the lock.

Who should be notified and what actions should be taken?

Answer:

The Operations key controller (or OWC) shall be notified Document the broken key in the Key Control Log or Key inventory record.

Attempt to retrieve the broken parts of the key, they will be retained until the lock is replaced.

Reference Use Allowed? Yes Reference 1 NO-I-11O Section 5.6.B Comments:

Satisfactory L l Unsatisfactory Candidate 4 of 4 ADMIN #1 Questions Security Revised 05/30/02

NO-i-110 Calvert Cliffs Key and Lock Control Revision 6 Page 8 of 30 4.0 RESPONSIBILITIES - (Continued) 4.8 Mechanical Maintenance responsibilities include controlling the keys listed in Attachment 7, Mechanical Maintenance Section.

4.9 Maintenance Support Section responsibilities include controlling the keys listed on.

4.10 Key Controllers are assigned by the General Supervisor of the group controlling the space with responsibilities which include the following:

Performance of Inventories according to section 5.9.

Documentation of lost or broken keys.

Documentation of replacement or deletion of obsolete keys.

Completion and Maintenance of Key control cards.

Completion and Maintenance of Key inventory records.

Completion and Maintenance of Key control logs.

5.0 PROCESS 5.1 Issuing Keys A.

Keys to vital equipment, safety related equipment or areas housing vital or safety related equipment inside the protected area shall be issued to BGE Calvert Cliffs personnel only.

B.

Exceptions to 5..A shall be authorized in writing by the Supervisor of the controlling group. This written authorization shall specify the following items:

Keys the individual may be issued.

Duration of the authorization.

Reason for the authorization.

NOTE This will allow an individual to act as a representative of the controlling group with respect to obtaining specific keys and holds the individual responsible for granting others access to the area or equipment.

1.

The written authorization shall be maintained with the Key Control Log until its expiration or cancellation.

NO-i-i 10 Calvert Cliffs Key and Lock Control Revision 6 Page 9 of 30 5.1 Issuing Keys (Continued)

C.

Authorized personnel requesting a controlled key shall contact the group controlling the area to obtain the necessary key.

1.

The controlling group representative shall issue the key to the requesting individual using Attachment 11 or 12 as appropriate.

D.

Personnel not authorized to be assigned keys shall request access from the group controlling the area.

E.

All keys to vital equipment, safety related equipment or areas housing this equipment shall be returned to the controlling group and stored in that group's key cabinet. This shall be completed prior to leaving the protected area or site if the controlling group's key cabinet is located outside the protected area. [B05101 Exceptions to the above are key rings assigned to shift personnel. (e.g., Operations, Safety Services, Security, Chemistry, Radiation Safety, Maintenance, Tool Attendants).

F.

Keys controlling access to High and Very High Radiation Areas restrict access for radiological safety purposes only. These keys do not control access to critical or safety related equipment or areas. [BOS10l G.

A High Radiation Area Master Key is issued to the Unit 1 and Unit 2 Auxiliary Building Operator's key ring for emergency purposes only. This master key operates only High (not very high radiation locks) Radiation Area locks.

NOTE This step is not applicable for very high radiation area keys.

H.

The following individuals are authorized to issue high radiation area keys:

Radiation Safety Supervisor Principal Radiation Safety Technician Qualified Radiation Safety Shift Technician Special Work Permit Coordinator Radiation Control Shift Supervisor Operations Shift Manager (in an emergency)

Radiation Protection Director during implementation of the Emergency Response Plan Nuclear Security Supervisor (in an emergency)

Calvert Cliffs Key and Lock Control NO-I-1 10 Revision 6 Page 17 of 30 ATTACHMENT 1, NUCLEAR OPERATIONS Diesel Generators: Access, Local/Remote AFAS: Cabinets, Bypass Keys ESFAS: Cabinets, Bypass Keys RPS: Trip Breakers, Bypass 1/2 C43 A&B Doors Operations Locks Safe Shutdown Key Lockers Pressurizer Heater Controls 1/2 C43 Feedwater MOV Override OPs Safety Related Storage Portable Lantern Lockers Inverter Interlock Lube Oil Storage RCS Sample Points AFW Pump Trip Throttle Override Containment Sump MOV Override Fuel Handling Equipment SWAC Local/Remote Cavity Cooling Dampers Locked Valves Fire Controls Containment Air Coolers 500 KV Breaker Cabinet in Switchyard GE-75 Breaker Cubical Pipe Tunnel Door Hydrogen Purge Main Turbine Overspeed & Trip Bypass Generator and Unit Protection Solid Waste Panel EHC Flow Control SGFP Thrust Operations Shift Manager HRA Key Control Room HVAC Equipment Room Control Room Ventilation Inlet and Exhaust Roof Hatches Smoke Removal Intake Roof Hatch Protectowire Cable Spreading Room Halon Main/Reserve First Aid Room I C/2C Cable Chase/NSB Master PA Fire Pump House Fire Doors (Except as specified on other attachments)

Fire Equipment Lockups Fire System Valves Outside Hose Cabinets Halon Panels South Service Building Isolation Valve Room IOB Isolation Valve Room Fire Alarm Panels (All Buildings)

Cable Chase Doors Alarm Pull Boxes

Calvert Cliffs Key and Lock Control Revision 6 Page 12 of 30 5.5 Key Control Log A.

A Key Control Log similar to Attachment 11 shall be maintained by each group controlling and holding keys.

B.

An entry shall be made in the Key Control Log whenever a key is removed from the Key Control Cabinet. Except as follows:

1.

Keys to locks in the Control Room may be kept in either their respective handswitch or the Control Room Key Locker.

2.

Keys kept in their handswitches do not need to be entered into the Key Control Log.

3.

Keys on key rings do not require Key Control Log entries.

C.

Except as noted in 5.5.B, whenever a key is requested the individual responsible for the key cabinet or a designated representative shall ensure the Key Control Log issue section is completed. On return of the key, the responsible individual shall complete the returned section of the Key Control Log.

D.

High and Very High Radiation Area Keys shall be controlled by Radiation Safety using 2, High and Very High Radiation Area Key Control Log. [B05111 E.

At the end of each day the Attachment 12(s), High and Very High Radiation Area Key Control Log, records shall be reviewed and reconciled to ensure all keys have been accounted for or returned.

NOTE If a High or Very High Radiation Area Key is lost, stolen or broken, then follow actions in Steps 5.6.E and F.

5.6 Lost, Stolen or Broken Keys [BO5121 A.

Lost, stolen or broken keys shall be evaluated for documentation according to QL-2-100, Issue Reporting and Assessment.

B.

Personnel identifying broken or lost keys shall complete the following:

1.

Notify the key controller for the group responsible for that particular key as soon as possible.

2.

The key controller shall document the lost, stolen or broken key in the Key Control Log or Key Inventory Record.

3.

Retrievable pieces of a broken key shall be returned to the key controller for that group.

4.

If a security key is broken, all pieces of the key shall be returned to Nuclear Security. If part of the key is still in the lock, stay next to the lock and notify Nuclear Security immediately.

5.

When the broken key is replaced or the lock and key are replaced the pieces of the key can be destroyed by the key controller. [B05121

Calvert Cliffs Nuclear Power Plant ADMIN A2 Topics Maintenance Ability to Analyze the effect of maintenance activities on LCO status K/A 2.2.24 [3.8]

Question a:

Unit-I is at 100% power. 12 Saltwater header must be taken out of service for maintenance on the heat exchangers. What action statements are required to be entered?

IZ ISatisfactory Unsatisfactory Candidate 1 of 4 ADM1N #2 Questions Maintenance Revised 05/30/02

Calvert Cliffs Nuclear Power Plant ADMIN A2 Topics Maintenance Ability to Analyze the effect of maintenance activities on LCO status K/A 2.2.24 [3.8]

Question a:

Unitl is at 100% power. 12 Saltwater header must be taken out of service for scheduled maintenance on the heat exchangers. What action statements are required to be entered?

Answer:

1. 3.5.2 action A 12 ECCS subsystem

2. 3.6.6 action A 12 Containment Spray subsystem

3. 3.6.6 action C one(B) Containment Cooling train

4. 3.7.5 action A 12 CC loop

5. 3.7.6 action B 12 SRW subsystem

6. 3.7.7 action A 12 SW subsystem

7. 3.8.1 action B 1B EDG Reference Use Allowed ? Yes

References:

01-29 Technical Specifications Comments:

Satisfactory Unsatisfactory Candidate 2 of 4 ADMIN #2 Questions Maintenance Revised 05/30/02

Calvert Cliffs Nuclear Power Plant ADMIN A2 Topics Maintenance Knowledge of the process for managing maintenance activities during power operations.

K/A 2.2.17 (3.5)

Question b:

In addition to entering the applicable LCOs, what other tasks must be performed prior to taking the SW header out of service?

Satisfactory l

Z Unsatisfactory Candidate 3 of 4 ADMIN #2 Questions Maintenance Revised 05/30/02

Calvert Cliffs Nuclear Power Plant ADMIN A2 Topics Maintenance Knowledge of the process for managing maintenance activities during power operations.

KIA 2.2.17 (3.5)

Question b:

In addition to entering the applicable LCOs, what other tasks must be performed prior to taking the SW header out of service?

Answer:

Operability of the redundant components must be verified operable per 01-49 and documented in the CRO logs. The lB EDG must be taken out of service. Verify that 11 CC heat exchanger is in service. Verify seal water is available to the operating Circulating water pumps.

Reference Use Allowed? YES Reference 1 NO-1-200 Section 5.4.B, OI-29 Comments:

Satisfactory Unsatisfactory Candidate 4 of 4 ADMIN #2 Questions Maintenance Revised 05/30/02

01-29 SALTWATER SYSTEM Rev. 48/Unit 1 Page 71 of 220 6.8 SHUTDOWN OF 12 SALTWATER HEADER [CONTINUOUS USEl A.

Initial Conditions

1.

At least one Component Cooling Pump in service.

2.

11 Component Cooling Heat Exchanger is available to be placed in service.

3.

Saltwater system aligned to supply both Component Cooling Heat Exchangers with one Component Cooling Heat Exchanger on service.

4.

11 A AND 1 1 B Service Water Heat Exchangers are in service.

5.

13 SRW Pump is capable of being aligned to both SRW Headers.

6.

IF 1A Diesel Generator is inoperable, THEN ALL of the following requirements have been met:

Cleaning of 1 2A or 1 2B Service Water Heat Exchanger is deemed absolutely necessary by Shift Manager Equipment needed for heat exchanger cleaning is staged at 12A or 12B Service Water Heat Exchanger Plant is in Mode 5, Mode 6, or defueled Tech Specs 3.4.7, 3.4.8, 3.8.2, 3.8.10, 3.9.4, 3.9.5 and TRM 15.1.3 have been reviewed and complied with

7.

1 B Diesel Generator is shutdown and 1 B DG OUT BKR, 152-1403, is open.

B.

Procedure

1.

IF 1 A DG is required to remain in service per Tech Specs, THEN PERFORM the following:

a. PERFORM operability verification of ZA train equipment PER 01-49, OPERABILITY VERIFICATION.

b. ENSURE that 01-49, OPERABILITY VERIFICATION, is performed every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> while 12 saltwater subsystem is secured, by scheduling it on the Shift Turnover Information Sheet. [B01 05]

01-29 SALTWATER SYSTEM Rev. 48lUnit 1 Page 72 of 220 6.8.8 Procedure (Continued)

2.

IF 12 Component Cooling Heat Exchanger is on service, ThEN PERFORM the following:

a. IF it is desired to bypass the CVCS ion exchangers, ThEN PLACE IX BYPASS, 1-CVC-520-CV, to BYPASS AND RECORD stop time in the CVCS Ion Exchanger and Filter Log. [10018] [B0207J

b. THROTTLE OPEN 11 COMP CLG HX SALTWATER FLOW CONTR, 1 -HIC-5206, as necessary to establish saltwater flow through the Component Cooling Heat Exchanger.

c. OPEN 11 CC HX CC OUT, 1 -CC-3824-CV.

d. SHUT 12 CC HX CC OUT, 1 -CC-3826-CV.

e. CHECK (1 C1 3) 'COMPT CLG PPS DISCH PRESS LO' annunciator clear.

f.

SHUT 12 COMP CLG HX SALTWATER FLOW CONTR, 1-HIC-5208.

NOTE For optimum Reactor Coolant Pump seal life performance, controlled bleed-off temperature must be maintained between 1100 and 2000 F.

g. ADJUST11 COMP CLG HX SALTWATER FLOW CONTR, 1-HIC-5206, to maintain the Component Cooling Heat Exchanger outlet temperature approximately 950 F.

CAUTION RCS boron concentration will be affected when CVCS ion exchangers are returned to service if the Letdown heat exchanger outlet temperature has changed since they were bypassed. [80270]

Lower Letdown system temperature will add positive reactivity.

Higher Letdown system temperature will add negative reactivity.

h. IF CVCS Ion Exchangers were bypassed in step 2.a, AND WHEN desired, THEN PERFORM the following:

(1) CHECK the Letdown Heat Exchanger outlet temperature is less than or equal to 1200 F AND approximately the temperature prior to removal.

(2) PLACE IX BYPASS, 1-CVC-520-CV, to AUTO.

(3) RECORD the flowrate in the CVCS Ion Exchanger and Filter Log.

[80018]

01-29 SALTWATER SYSTEM Rev. 48lUnit 1 Page 73 of 220 6.8.B Procedure (Continued)

3.

IF the Unit is in Mode 5 or Mode 6, AND 12 saltwater subsystem is to be taken out of service for any reason, THEN ENSURE the following: [60033]

RCS water level is raised to maximum allowable level RCS temperature is lowered as much as practical Containment closure is set PER STP-0-55A-1, CONTAINMENT CLOSURE VERIFICATION or Containment integrity established per STP 0-55-1, CONTAINMENT INTEGRITY VERIFICATION.

• The OC DG is available OR SMECO is aligned into plant PER 01-27E, SMECO OFFSITE POWER SYSTEM, Section ENERGIZING 23 13KV SERVICE BUS FROM SMECO POWER SUPPLY SYSTEM IF Steam Generators are NOT available PER OP-7, SHUTDOWN OPERATIONS, THEN one of the following conditions is met:

RWT level is greater than 35 feet Refueling Pool level is greater than 57 foot elevation Service Water System temperature is lowered as much as possible

4.

IF 12 SW Header is supplying Seal Water, THEN PLACE Circulating Water Pump Seal Water Supply Header in service as follows:

11 Saltwater Subsystem:

a. ENSURE OPEN 11 SW HDR TO SEAL WATER BS-5250 ISOL VLV, 1 -SW-375.

b. ENSURE SHUT 12 SW HDR TO SEAL WATER BS-5250 ISOL VLV, 1 -SW-377.

OR

• IF Circulating Water Pumps are in service, THEN ALIGN Circulating Water Pump seal water supply to alternate source PER 01-14A, CIRCULATING WATER, Section ALIGNING ALTERNATE CW PP SEAL WATER SYSTEM FROM PSW SUPPLY.

OR Circulating water pumps have been secured PER 01-14A, CIRCULATING WATER.

SALTWATER SYSTEM Rev. 48/Unit 1 Page 74 of 220 j

6.8.6 Procedure (Continued)

5.

ENSURE the Technical Specification requirements are met for the following equipment being removed from service:

EQUIPMENT TS MODE "B" Train ECCS Subsystem 3.5.2 1,2.3 (PZR press Ž1750 psia)

"B" Train ECCS Shutdown 3.5.3 3(<1750 PSIA)&4 "B"

Train Containment Spray and 3.6.6 1,2.3(CS only req. operable "B" Train Containment Cooling with PZR press Ž1750 psia) 12 Component Cooling Subsytem 3.7.5 1-4 12 Service Water Subsystem 3.7.6 1-4 12 Saltwater Subsystem 3.7.7 1-4 12 Shutdown Cooling Loop 3.4.6 4

12 Shutdown Cooling.Loop 3.4.7

5. loops filled 12 Shutdown Cooling Loop 3.4.8 5, loops not filled SOC and Coolant Circulation 3.9.4 6

High Water Level SDC and Coolant Circulation 3.9.5 6

Low Water Level 1B Diesel Generator 3.8.1.B 1-4 1B Diesel Generator 3.8.2 5 & 6

6.

IF ECCS Cooler maintenance is to be performed, THEN PLACE 12 WEST ECCS PP RM CLG FAN, 1-HS-5404A to STOP.

7.

ENSURE the following 12 ECCS Air Cooler Saltwater valves are CLOSED:

1-HS-5173, 12 ECCS AIR CLR INLET 1-SW-5173-CV 1-HS-5176, 12 ECCS AIR CLR OUT VLVS

CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE OI-36-ADMIN(NEW)

TASK:

PURPOSE:

RADCON Starting an Alternate Purge of Containment Evaluates an Operator's ability to identify Radiological Control requirements associated with a task JOB PERFORMANCE MEASURE CALVERT CLIFFS NUCLEAR POWER PLANT LICENSED OPERATOR TRAINING Rev. 2

Page 2 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE 01-36-ADMIN (NEW)

TASK:

Starting an Alternate Purge of Containment PERFORMERS NAME:

APPLICABILITY:

SRO/RO PREREQUISITES:

Completion of the Initial License classroom and simulator training.

EVALUATION LOCATION:

PLANT SIMULATOR EVALUATION METHOD:

ACTUAL PERFORMANCE DEMONSTRAI ESTIMATED TIME ACTUAL TIME TIME TO COMPLETE JPM:

TO COMPLETE JPM:

5 MINUTES MINUTES D

TASK LEVEL:

TRAIN CONTROL ROOM

'E PERFORMANCE CRITICAL TASK:

N;O TOOLS AND EQUIPMENT:

None REFERENCE PROCEDURE(S):

RP-1-I00, section 5.2 TASK STANDARDS:

This JPM is complete when the candidate determines that additional radiological control requirements must be met to complete the task..

Page 3 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE OI-36-ADMIN (NEW)

TASK:

Starting an Alternate Purge of Containment DIRECTIONS TO EVALUATOR:

NOTE: THIS JPMSHOULD BE PERFORMED IMMEDL4 TEL YAFTER OI-36-1.

BEFOREEXITING THE 5' LEVEL OF THE AUXILIRYBUILDING

1.

Read the "Directions to Trainee" to the trainee.

2.

Note the time that the task is started. As the task proceeds, indicate completion of each element using the Standard criteria and the following notation:

- "S" for satisfactory completion

- "U" for unsatisfactory completion

- "N" if not observed OR not verifiable Critical elements must be observed or the evaluation is invalid.

3.

When the Terminating Cue is reached, tell the trainee that no further actions are necessary. Note the completion time.

4.

Document any instances of failure to comply with industrial safety practices, radiation safety practices and use of event free tools in the Notes area.

Immediately correct any actions that could result in violation of a safety procedure or personnel injury. NOTE: Violation of safety procedures will result in failure of the JPM.

5.

Questions to clarify actions taken should be asked after completion of the task.

6.

Indicate whether the task was completed satisfactorily on the basis of correct performance of all critical elements and completion of the task within the Estimated Time to Complete for Time Critical tasks.

7.

This JPM contains the steps, notes, cautions, and standards that are applicable to the initial conditions specified in this JPM. Steps that do not directly relate to this JPM, but appear in the procedure, are not listed here. It is the responsibility of the evaluator and/or observer to become familiar with the procedure prior to use of this JPM.

Page 4 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE OI-36-ADMIN (NEW)

TASK:

Starting an Alternate Purge of Containment

8.

Document any instances of when the near miss threshold was reached due to inappropriate personnel actions/inactions or procedural quality as a result of the following:

Reactivity Management Unplanned power changes > 1%

Reduction of boron concentration of > 5% delta rho Radiation Safety Preventable PCIs Personnel Safety Operations near miss accident Reactor Safety Automatic trip near miss Actions required by operators to prevent an automatic trip Valid RPS trip or pre-trip alarms due to a plant transient Configuration Control Valve mispositioning or loss of control of tagging boundary resulting in loss of system inventory

Page 5 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE OI-36-ADMIN (NEW)

TASK:

Starting an Alternate Purge of Containment JPM STANDARDS (List of minimum Standard Practices for common evolutions at CCNPP)

If non-emergency condition, dispatches a PO to verify pump is ready to be started.

Identify the Control Switch and Indicating Lights, using authorized identification.

Operate the Control Switch, to START, and check expected Indicating Light response.

Check proper pump operation (as applicable):

Motor amps Pump discharge pressure System flow ActivationlClearing of applicable Annunciators (e.g.; Hi Disch Press, Lo Hdr Press)

Identify the Control Switch and Indicating Lights, using authorized identification.

Operate the Control Switch, to STOP, and check expected Indicating Light response.

Check expected system response (e.g.; flow, pressure, level)

Identify the Control Switch and Indicating Lights, using authorized identification.

Select the Control Switch to the desired position.

Check Valve/Breaker position, using position Indicating Lights.

Check expected system response (e.g.; flow, pressure, level, volts, amps, KW)

Identify the Valve/Breaker Indicating Lights, using authorized identification.

Check the Valve/Breaker is in the correct position.

If Valve/Breaker is not in correct position, report Valve/Breaker position to CRS.

Identify the Valve/Breaker Indicating Lights, using authorized identification.

Check the Valve/Breaker is in the correct position.

If Valve/Breaker is not in correct position, operates Valve/Breaker to correct position.

Verify the following:

Suction Valve open Discharge Valve position (as applicable)

Miniflow Valve position (as applicable)

Pump and Motor oil levels are normal Adequate Suction Pressure Identify the Control Switch and Indicating Lights, using authorized identification.

Page 6 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE 01-36-ADMIN (NEW)

TASK:

Starting an Alternate Purge of Containment Operate the Control Switch, to START, and check expected Indicating Light response.

Check for proper Pump operation (as applicable):

Smooth, quiet operation consistent with pump history Oil level remains good Proper seal leakoff Proper discharge pressure Expected system flow Identify the Control Switch and Indicating Lights, using authorized identification.

Operate the Control Switch, to STOP, and check expected Indicating Light response.

Check expected system response (e.g.; flow, pressure, level).

~ 4 Opr.tig a MAnu1uld ss.<

.H Identify the Valve, using authorized identification.

Operate the Valve and check expected position indication change (e.g.; stem rise, pointer).

Check expected System response (e.g.; fluid flow sounds, pressure changes, tank levels).

Identify the Control Switch and Indicating Lights (if applicable), using authorized identification.

Operate the Control Switch and check expected Indicating Light response.

Check expected System response (e.g.; flow, pressure, levels, volts, amps).

-g ~g ~S:-fflff.4 Identify the Valve/Breaker, using authonized identification.

Check the Valve/Breaker is in the correct position, using appropriate position indication (e.g.;

pointer, stem rise, flags, indicating lights).

If Valve/Breaker is not in correct position, report Valve/Breaker position to Control Room.

4X 110 Lcal veMynI~~%st~

K Identify the Valve/Breaker, using authorized identification.

Check the Valve/Breaker is in the correct position, using appropriate position indication (e.g.;

pointer, stem rise, flags, indicating lights).

If Valve/Breaker is not in correct position, operates Valve/Breaker to correct position.

Page 7 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE OI-36-ADMIN(NEW)

ELEMENT

(* = CRITICAL STEP)

STANDARD TIME START Locate 01-36 Section 6.7, Step B.6 Without error CUE: 2-HS-5289 has been placed in START by the CRO.

CUE: Position cannot be determined from the floor the level.

Note to Evaluator: Do not allow the candidate to climb anv ladder without approval Irom Rad Safety.

Locates 2-CPA-5289-DAMP piston operator in 5' overhead. Determines RAD SAFETY must be contacted to survey area and determine requirements for climbing in overhead.

TIME STOP TERMINATING CUE:

This JPM is complete when the candidate contacts RADCON for additional guidance. No further actions required.

l

CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE OI-36-ADMIN(NEW)

TASK:

Starting an Alternate Purge of Containment Document below any instances of failure to comply with industrial safety practices, radiation safety practices and use of event free tools. NOTE: Violation of safety procedures will result in failure of the JPM.

NOTES:

DID A NEAR MISS OCCUR DUE TO INAPPROPRIATE PERSONNEL ACTIONS/INACTIONS OR PROCEDURAL QUALITY?

YES (If yes, provide comments below)

COMMENTS:

NO The operator's performance was evaluated against the standards contained in this JPM and determined to be SATISFACTORY UNSATISFACTORY EVALUATOR'S SIGNATURE:

DATE:

CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE DIRECTIONS TO TRAINEE:

1.

To complete the task successfully, you must:

• perform each critical element correctly. You must inform the evaluator of the indications you are monitoring. Where necessary, consider the evaluator to be the CRS.

• comply with industrial safety practices, radiation safety practices and use of event free tools. NOTE: Violation of safety procedures will result in failure of the JPM.

2.

Initial Conditions:

a.

Unit 2 is in a refueling outage.

b.

An approved Containment purge permit is held by the CRO.

c.

You are performing the duties of Unit 2 ABO.

d.

The CRO has started the Containment Purge Exhaust Fan.

3.

Initiating Cue: You are directed by the CRO to locally verify the purge exhaust damper is open per 01-36 Section 6.7, Step B.6 Are there any questions? You may begin.

01-36 CONTAINMENT PURGE SYSTEM Rev. 25 Page 27 of 32 6.7.B Procedure (Continued)

NOTE

• The key will be captured in the Test/Alt Purge position.

• The Purge Exh Fan Test/Alt Purge handswitch is located on breaker52-10311 (52-20311).

2.

PLACE Purge Exh Fan TEST/ALT PURGE handswitch, 1 (2)-HS-5289A, in TEST/ALT PURGE.

3.

NOTIFY Radiation Safety Supervision that the plant will be initiating an alternate purge of containment

4.

ENTER Containment Purge alarm values from the Gaseous Waste Release Permit in the Plant Computer. (R5415A! U-1, R5415B! U-2)

5.

IF Containment Average air temperature is less than or equal to 450 F, 25100 THEN ENSURE plant heating is aligned to Purge Supply Fan PER APPENDIX 2, 25103 PLANT HEATING ALIGNMENT TO CONTAINMENT PURGE. [B0782]

a. I plant heating is NOTavailable, 25100 THEN Purge operation is not allowable.

6.

PLACE handswitch CNTMT PURGE EXH FAN, 1 (2)-HS-5289, in START AND Locally VERIFY CNTMT PURGE EXH AIR OPERATED DAMPER, 1(2)-CPA-5289DAMP, is FULL OPEN by verifying the piston operator is fully extended (-3.5 in.).

a. CHECK the TEST/ALT PURGE amber light is illuminated.

CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE ERPIP-3-7 (NEW)

TASK:

PURPOSE:

Determine appropriate emergency response actions per the ERPIP while maintaining an overview of plant conditions Evaluates an Operator's Ability to Determine that an Alert Condition Exists, Complete the Initial Notification Form, and Notify On-Site Personnel JOB PERFORMANCE MEASURE CALVERT CLIFFS NUCLEAR POWER PLANT LICENSED OPERATOR TRAINING Rev. 0

Page 2 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE ERPIIP-3-7 (NEW)

TASK:

Determine appropriate emergency response actions per the ERPIP while maintaining an overview of plant conditions PERFORMER'S NAME:

APPLICABILITY:

RO and SRO PREREQUISITES:

Completion of the knowledge requirement of the Initial License class training program for Emergency Response Plan Implementation Procedures.

EVALUATION LOCATION:

PLANT SIMULATOR CONTROL ROOM EVALUATION METHOD:

ACTUAL PERFORMANCE

_DEMONSTRATE PERFORMANCE ESTIMATED TIME ACTUAL TIME TIME CRITICAL TASK:

TO COMPLETE JPM:

TO COMPLETE JPM:

10 MiNUTES MINUTES NO TASK LEVEL:

LEVEL 1 TOOLS AND EQUIPMENT:

Blank copy of ERPIP 3.0 Attachment 3, Initial Notification Form REFERENCE PROCEDURE(S):

ERPIP 3.0 TASK STANDARDS:

This JPM is complete when an EAL classification is determined based on given plant conditions, initial notification form completed, and on-site notification made.

Page 3 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE ERPIP-3-7 (NEW)

TASK:

Determine appropriate emergency response actions per the ERPIP while maintaining an overview of plant conditions DIRECTIONS TO EVALUATOR:

1.

Read the "Directions to Trainee" to the trainee.

2.

Note the time that the task is started. As the task proceeds, indicate completion of each element using the Standard criteria and the following notation:

- "S" for satisfactory completion

- "U" for unsatisfactory completion

- "N" if not observed OR not verifiable Critical elements must be observed or the evaluation is invalid.

3.

When the Terminating Cue is reached, tell the trainee that no further actions are necessary. Note the completion time.

4.

Document any instances of failure to comply with industrial safety practices, radiation safety practices and use of event free tools in the Notes area.

Immediately correct any actions that could result in violation of a safety procedure or personnel injury. NOTE: Violation of safety procedures will result in failure of the JPM.

5.

Questions to clarify actions taken should be asked after completion of the task.

6.

Indicate whether the task was completed satisfactorily on the basis of correct performance of all critical elements and completion of the task within the Estimated Time to Complete for Time Critical tasks.

7.

This JPM contains the steps, notes, cautions, and standards that are applicable to the initial conditions specified in this JPM. Steps that do not directly relate to this JPM, but appear in the procedure, are not listed here. It is the responsibility of the evaluator and/or observer to become familiar with the procedure prior to use of this JPM.

Page 4 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE ERPIP-3-7 (NEW)

TASK:

Determine appropriate emergency response actions per the ERPIP while maintaining an overview of plant conditions

8.

Document any instances of when the near miss threshold was reached due to inappropriate personnel actions/inactions or procedural quality as a result of the following:

Reactivity Management Unplanned power changes > 1%

Reduction of boron concentration of > 5% delta rho Radiation Safety Preventable PCIs Personnel Safety Operations near miss accident Reactor Safety Automatic trip near miss Actions required by operators to prevent an automatic trip Valid RPS trip or pre-trip alarms due to a plant transient Configuration Control Valve mispositioning or loss of control of tagging boundary resulting in loss of system inventory

Page 5 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE ERPIP-3-7 (NEW)

TASK:

Determine appropriate emergency response actions per the ERPIP while maintaining an overview of plant conditions JPM STANDARDS (List of minimum Standard Practices for common evolutions at CCNPP)

If non-emergency condition, dispatches a PO to verify pump is ready to be started.

Identify the Control Switch and Indicating Lights, using authorized identification.

Operate the Control Switch, to START, and check expected Indicating Light response.

Check proper pump operation (as applicable):

Motor amps Pump discharge pressure System flow Activation/Clearing of applicable Annunciators (e.g.; Hi Disch Press, Lo Hdr Press)

Identify the Control Switch and Indicating Lights, using authorized identification.

Operate the Control Switch, to STOP, and check expected Indicating Light response.

Check expected system response (e.g.; flow, pressure, level) ss>2-XB~~n B....i 12.

.B....B Identify the Control Switch and Indicating Lights, using authorized identification.

Select the Control Switch to the desired position.

Check Valve/Breaker position, using position Indicating Lights.

Check expected system response (e.g.; flow, pressure, level, volts, amps, KW)

Identify the Valve/Breaker Indicating Lights, using authorized identification.

Check the Valve/Breaker is in the correct position.

If Valve/Breaker is not in correct position, report Valve/Breaker position to CRS.

BX esi2s2s22ix>BB Identify the Valve/Breaker Indicating Lights, using authorized identification.

Check the Valve/Breaker is in the correct position.

If Valve/Breaker is not in correct position, operates Valve/Breaker to correct position.

Verify the following:

Suction Valve open Discharge Valve position (as applicable)

Minifiow Valve position (as applicable)

Pump and Motor oil levels are normal Adequate Suction Pressure Identify the Control Switch and Indicating Lights, using authorized identification.

Page 6 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE ERPIP-3-7 (NEW)

TASK:

Determine appropriate emergency response actions per the ERPIP while maintaining an overview of plant conditions Operate the Control Switch, to START, and check expected Indicating Light response.

Check for proper Pump operation (as applicable):

Smooth, quiet operation consistent with pump history Oil level remains good Proper seal leakoff Proper discharge pressure Expected system flow

,,f,,.4*

yy 5,

rrgs.

Identify the Control Switch and Indicating Lights, using authorized identification.

Operate the Control Switch, to STOP, and check expected Indicating Light response.

Check expected system response (e.g.; flow, pressure, level).

Operating a

7 1-1mnul

.'Vl.e Identify the Valve, using authorized identification.

Operate the Valve and check expected position indication change (e.g.; stem rise, pointer).

Check expected System response (e.g.; fluid flow sounds, pressure changes, tank levels).

Identify the Control Switch and Indicating Lights (if applicable), using authorized identification.

Operate the Control Switch and check expected Indicating Light response.

Check expected System response (e.g.; flow, pressure, levels, volts, amps).

Identify the Valve/Breaker, using authorized identification.

Check the Valve/Breaker is in the correct position, using appropriate position indication (e.g.;

pointer, stem rise, flags, indicating lights).

If Valve/Breaker is not in correct position, report Valve/Breaker position to Control Room.

ad...; '5 5

g,

g g

55 g

g 5

5gtxg g 52 g

Identify the Valve/Breaker, using authorized identification.

Check the Valve/Breaker is in the correct position, using appropriate position indication (e.g.;

pointer, stem rise, flags, indicating lights).

If Valve/Breaker is not in correct position, operates Valve/Breaker to correct position.

Page 7 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE ERPIP-3-7 (NEW)

ELEMENT

(* = CRITICAL STEP)

STANDARD TIME START

1.

Identify and locate ERPIP.

2.

Refers to Immediate Actions and identifies the appropriate category from the listing and go to the appropriate Attachment.

Same as element.

Selects and goes to attachment 2, Emergency Classification.

ATTACHMENT 2 EMERGENCY CLASSIFICATION A.

CLASSIFY THE EMERGENCY NOTE:

The decision to classify an emergency may NOT be delegated.

LO EALUAE vz~i~iorw

't~tavh~nt Determines an ALERT IB.

I EMENT AMtRGNCY RESPONE PLAN.

ATOEMERGENCY classification is warranted under FISSION PRODUCT BARRIER DEGRADATION, based on 1/3 barriers affected, EOP-6 is implemented for RCS leakage, B.

IMPLEMENT EMERGENCY RESPONSE PLAN ACTIONS (ATTACHMENT 2) 1.0 IF an EAL is satisfied THEN OBTAIN an Initial Notification form (Attachment 3 to this procedure). GO TO the respective classification tab.

Determines Attachment 11 is applicable CUE: Provide examinee with a copy of ERPIP 3.0 Attachment3, Initial Notification NOTE TO EVALUA TOR:

Thisataffckment 3is your copy to follow the operator's actions during this JPM.

ATTACHMENT 3 INITIAL NOTIFICATION

1.

Complete Item 1.

Circles "is not" in Item 1

2.

Complete Item 2.

Inserts name in Item 2

Page 8 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE ERPIP-3-7 (NEW)

ELEMENT

(* = CRITICAL STEP)

STANDARD Checks "Alert" in Item 5 Enters EAL code BAI and circles EAL number NA, and two digit Event Code 61 in Item 7 Checks "Is Being Released" and "From the Plant" Checks "Airborne" Checks "None" in Item 10 Checks "None" in Item 11 Circles "is not" in Item 12 Enter "Time" and "Date" Must be completed last Enters signature in in Sec signature location.

9.

Complete Item 12.

n IJUL1il notrnanon form.

A.

COMPLETE THE INITIAL NOTIFICATION FORM (ATTACHMENT 11 ALERT) 1.0 COMPLETE Initial Notification form (Attachment 3) as follows (items not mentioned are self-explanatory).

a.

Item 6, Time Declared: complete this last.

Obtains Attachment 3 from the evaluator or the "Extra Forms" book.

No action required.

b.

Item 7, Nature of Incident:

NOTE EAL code and number and event code are ERPIIP 3.0, Attachment 1, EALs, Page 1 Enter EAL code Circle EAL number Enter two digit event code Chooses and records BAI Fission Product Barrier Degradation on Attachment 3.

Circles N/A for number and enters 61 for two digit event code.

Page 9 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE ERPIiP-3-7 (NEW)

ELEMENT STANDARD

(* = CRITICAL STEP)

c.

Item 8, Radioactivity: radioactivity is being/has been released if any of the following conditions are/have been met:

Determines radioactivity is being released.

(1) the release flowpath monitor is/was in alarm (2) the release is/was greater than Technical Spec limits (3) the release is/was accidental

d.

Item 10, Population Affected: check "None".

e.

Item 11, Protective Actions Recommended: select a protective action from Attachment 5, Prompt Protective Action Recommendation.

No action required.

Determines Step is N/A ATTACHMENT 11 (ALERT)

B.

HAVE THE INITIAL NOTIFICATION TRANSMITTED Directions given.

C.

NOTIFY ONSITE PERSONNEL Note to Evaluator: If they choose to delegate notification, then critical step is complete; if they chose to do it themselves, Step a & b must be completed A.

NOTIFY ONSITE PERSONNEL

Page 10 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE ERPIP-3-7 (NEW)

ELEMENT

(* = CRITICAL STEP)

STANDARD 1.0 Direct the Control Room Communicator to perform the following:

Sounds alarm for 5 seconds.

Makes the following announcement:

"An ALERT exists for Fission Product Barrier Degradation.

All personnel report to your assembly area immediately."

Sounds alarm for 5 seconds.

Makes the following announcement:

"An ALERT exists for Fission Product Barrier Degradation.

All personnel report to your assembly area immediately."

IKertJlk step C. 1.0.a and C. 1.0.b of this attachment once.

TIME STOP TERMINATING CUE:

This JPM is complete when an EAL classification is determined based on given plant conditions, initial notification form completed, and on-site notification made. No further actions are required.

Page 11 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE ERPIP-3-7 (NEW)

TASK:

Determine appropriate emergency response actions per the ERPIP while maintaining an overview of plant conditions Document below any instances of failure to comply with industrial safety practices, radiation safety practices and use of event free tools. NOTE: Violation of safety procedures will result in failure of the JPM.

NOTES:

DID A NEAR MISS OCCUR DUE TO INAPPROPRIATE PERSONNEL ACTIONS/INACTIONS OR PROCEDURAL QUALITY?

YES (If yes, provide comments below)

COMMENTS:

NO The operator's performance was evaluated against the standards contained in this JPM and determined to be SATISFACTORY UNSATISFACTORY EVALUATOR'S SIGNATURE:

DATE:

CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE DIRECTIONS TO TRAINEE:

1.

To complete the task successfully, you must:

• perform each critical element correctly. You must inform the evaluator of the indications you are monitoring. Where necessary, consider the evaluator to be the CRS.

• comply with industrial safety practices, radiation safety practices and use of event free tools. NOTE: Violation of safety procedures will result in failure of the JPM.

2.

Initial Conditions:

a.

Unit-I was at 100% power when the indications of a S/G tube leak prompted operators to enter AOP-2A. Estimated leak rate was 12 GPM.

b.

Condenser Off-gas and blowdown RMS were in alarm.

c.

During the shutdown, an automatic reactor trip occurred due to loss of offsite power.

d.

EOP-6 was implemented upon completion of EOP-0, for a SGTR on #11 S/G, a cooldown is in progress using atmospheric dump valves. #11 S/G has not been isolated.

e.

WRNGM (RIC-5415) is reading 5.56E2 IVC/sec.

f.

You are performing the duties of the Shift Manager.

3.

Initiating Cue: You are directed by EOP-6, to implement the ERPIP. Are there any questions? You may begin.

,1 INDICATORS FUEL CLAD BARRIER Loss -Not Applicable Potentiol Loss SF I EOP-8, Functional Recovery Procedure, can NOT meet (ore and RCS heat removal SAFETY FUNCTION acceptance criteria with recovery actions AND Shutdown Cooling is NOT in service STATUS/FUNCTIONAL RECOVERY Loss

((J Valid Core Exit Thermocouple readings GREATER THAN 1 200°F TEMPERATURE Potential Loss

[

Valid (ore Exit Thermocouple readings indicate superheat Loss FL Dose rote at one foot from post accident sample of AT LEAST 40 mrem/h OR

[T]

Valid RI-5317A/B reading of AT LEAST 3,500 rem/h within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after reactor shutdown OR RADIATION FL AT LEAST 5%

fuel clad damage os determined from core damage assessment OR F[

Coolant activity GREATER THAN 600 pui/cc DEQ 1 13 Poential Loss -Not Applicable COOLANT LEAKAGE Not Applkable PRESSURE Not Applicable Loss -Not Applicable REACTOR VESSEL WATER LEVEL Potential Loss f Valid RVLMS 29 inch light is on AND trending toward 10 inch light Any condition which in the SEC's judgment indicates loss or potential loss of the fuel dod barrie based on:

SEC JUDGEMENT

• Imminent barrier degradation (within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) due to safety system performance

- Degraded ability to monitor barriers 3425

ATTACHMENT 1 (PAGE 2 OF 2)

FISSION BARRIER REFERENCE TABLE (APPLIES TO MODE 1, 2, 3, 4 ONLY)

RCS BARRIER CNTMT BARRIER Loss Loss - Not Applicable nL EOP-8, Functional Recovery Procedure, is implemented from EOP-6, Steam Generator Tube Rupture Potential Loss -Not Applicable Potential Loss p

Uncontrolled RCS cooldiwn AND RCS pressure-temperature in the non-operating area (left of the (ooldown curve)

OR nElI EOP-8, Functional Recovery Procedure, can NOT meet core and R(S heat removal acceptance criteria with recovery actions AND Shutdown Cooling is NOT in service Loss Loss - Not Applicable i E] RCS Subcooling can NOT be maintained AT LEAST 251F Potential Loss Potential Loss

-Not Applicable jP Valid Core Exit Thermocouple readings GREATER THAN 13000F AND increasing Loss Lass Vols t A EOP-5 Loss of Coolant Accident, Or EOP 8, Functional Recovery Procedure, is ValidBreading of AT LEAST 5 rem/h within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> aerrearshutdown implemented AND radiation levels external to CNTMT can NOT meet acceptance criteria Potential Loss

- Not Applicable Potential lass

[I Valid 531 7A/B reading of AT LEAST 14,000 rem/h within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after reactor shutdown OR ES AT LEAST 20% clad damage as determined from core damage assessment OR EP EOP-A Loss of Coolant Accident, is implemented AND LOCA is NOT occurring within the (NTMT as indicated by Aux Building sump alarms or Aux Building RMS alarms Loss - Not Applicable Loss Potential Loss FL Leakage pathway exists from inside (NITMT to outside CNTMT P RCS leakage exceeds available CVCS capacity OR OR i d

e Steam Generator tube rupture in progress and an unexpected/uncontrolled release to the m

EOP-5 Loss of Coolant Acdent O

is implemented for R(S leakage environment from the of ected Steam Generator for GREATER THAN 15 minutes.

np EOP-6, Steam Generator Tube Rupture, is implemented for RCS leakage OR Potential Loss - Not Applicable E

EOP-8, Functional Recovery Procedure, is implemented for R(S leakage Loss III Rapid unexplained CNTMT pressure decrease following initial increase Not Applicable Potential loss

- X. (NTMT pressure of AT LEAST 50 PSIG AND increasing OR nP CNTMT H concentration of AT LEAST 4.0%

-, Apflabl~

-Not Appflcable'-

Any condition which in the SEC's judgment indicates loss or potential loss of the RCS barrier Any condition which in the SEC's judgment indicates loss or potential loss of the CNTMT based on:

barrier based on:

• Imminent barrier degradation (within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) due to safety system performance

• Imminent barrier degradation (within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) due to safety system performance

• Degraded ability to monitor barriers

- Degraded ability to monitor barriers

ERPIP 3.0 REV. 26 THREE BARRIERS AFFECTED L

P L

L P

CLAD RCS CTM 3/3

=

/

~YES l

ing BRE RS?

NO ocedure, is 3nce criteria TWO BARRIERS AFFECTED ictor shutdown L

P L

I PI L

P irring within the CLAD RCS CNTMT SITEI

`EMERGEN CY release to the lutes.

ONLY ONE BARRIER AFFECTED ALERT L

PI L

I L

IP CLAD RCS CNTMT CNTMT UNUSUAL EVENT nce

I GENERAL EMERGENCY J

SITE EMERGENCY EI ALERT ALERT I

RAI

1. Valid WRNGM (RIC-5415) reading of AT LEAST 3.2E+7 pu/sec for GREATER THAN 15 minutes

2. Valid Main Steam Effluent Monitor (Rl-5421, RI-5422) reading of AT LEAST 0.4 rem/h for GREATER THAN 15 minute!

3. Field survey dose rate reading of 10 mrem/h or greater at site boundary RA2

1. AOP-6E, Loss of Refueling Pool Level, is implemented AND valid Containment Radiation alarm (Rl-5316A/B/C/L

2. AOP-6D, Fuel Handling Incident, is implemented and ANY of the following:

• Valid Containment Radiation alarm (Rl-531 6A/B/C/D)

• Valid Fuel Handling Area Ventilation Exhaust Radiation Monitor (Rl-5420) reading of AT LEAST 2E+4 CPM

• Valid Spent Fuel Service Platform Monitor (RI-7025) reading of AT LEAST 100 mrem/h RA3

1. Valid Control Room Radiation Monitor (RI-5350) reading GREATER THAN 15 mrem/h

2. Exposure rate of 10 rem/h or greater in an Area of Concern for Safe Shutdown.

+

RUl

1. Valid WRNGM (RIC-5415) reading of AT LEAST 3.2E+5 pG/sec for GREATER THAN 60 minutes

2. Valid Main Vent Monitor (RI-5415) reading of AT LEAST 2E+5 (PM for GREATER THAN 60 minutes

3. Valid Waste Proaessing Monitor IRI-5410) reading of AT LEAST 4E+5 CPM for GREATER THAN 60 minutes

4. Valid Fuel Handling Area Ventilation Exhaust Radiation Monitor (RI-5420) reading of AT LEAST 3.4E+5 CPM for GREA THAN 60 minutes

5. Valid Access Control Monitor (RI-5425) reading off-scale high for GREATER THAN 60 minutes

6. Valid ECCS PP Roam Monitor (RI-5406) Reading Off-Scale high for GREATER THAN 60 Minutes RU2

1. AOP-6D Or AOP-6E is implemented AND any of the following:

I UNUSUAL EVENT I

C


"

\\\\__

,i

• Valid Fuel Handling Area Ventilation Exhaust Radiation Monitor alarm (RI-5420)

• Valid Spent Fuel Pool Area Monitor alarm (RI-7024)

• Valid Containment Radiation Monitor (RI-5316A/B/CID) reading of AT LEAST 100 mrem/h Valid unexpected rod monitor reading Affscole high OR GREATER THAN 1000 times normal reading 2.

RU3

1. Horizontal Storage Module (HSM) Access Door contact dose rate GREATER THAN 500 mrem/h

2. Horizontal Storage Module (HSM) Side Wall Door contact dose rate GREATER THAN 100 mrem/h

3. Any unplanned event outside the Auxiliary Building resulting in the breach of a Dry Shielded Canister (DSCI containing spent fuel

4. Dry Shielded Canister (DSCI Transfer (ask containing spent fuel has been dropped from the trailer 3424

Li-Li

\\2 VC1NT CCJfW&

I FISSION PRODUCT BARRIER DEGRADATION EQUIPMENT FAILURE

-I HAN 15 minutes.

1-5316A/B/UD)

-4 (PM BAI Mode 1, 2, 3, 4 See Fission Barrier Reference Table Loss or potential loss of EITHER Fuel (lad barrier OR RCS barrier QAI Mode 1, 2 Automatic reactor trip signal generated AND manual trip was required to trip the reactor.

QA2 Mode 5, 6

1. Uncontrolled RCS temperature increase of AT LEAST 1 0F that results in RCS temperature GREATER THAN 200'F

2. Inadvertent criticaldy as determined by valid wide range logarithmic channel indications 0A3 Mode 1 2 3, 4 Unplanned loss of 75% of main control board onnuncidtors for GREATER THAN 15 minutes AND EITHER of the follov

• Significant transient in progress

• SPDS AND plant computer are NOT Available OA4 Defueled Power to Spent Fuel Pool Cooling Pumps lost AND Spent Fuel Pool temperature increases to GREATER THAN 1 550F.

QAS Mode 1, 2 EOP-3, Loss of all Feedwater is implemented.

\\

/%t It tes 5 CPM for GREATER BUI Mode 1, 2, 3, 4 See Fission Borrier Reference Table Loss or potential loss of CNTMT barrier BU2 AOP-2A Excessive Reactor Coolant Leakage, is implemented for RCS leakage AND a mode change is required.

BU3 Fuel clad degradation indicated by R(S sample activity GREATER THAN Tech. Spec. 3.4.15 allowable limits and cooldown is required by the Tech. Spec.

Oul Mode 4, 5, 6

1. Entry into AOP-3B, Abnormal Shutdown Cooling Conditions, is required for GREATER THAN 15 minutes

2. Entry into AOP-1A, Inadvertent Boron Dilution, is required AND shutdown margin NOT maintained OU2 Mode 1, 2, 3, 4 Unplanned loss of 75% of main control board annunciators for GREATER THAN 15 Minutes QU3

1. Loss of ALL on-site electronic communications methods

2. Loss of ALL telephone communications with government agencies OU4 Mode 1, 2, 3, 4 Unit can NOT be brought to required mode within applicable LEO action statement time limits Ous Mode 1, 2 EOP-4, Excess Steam Demand Event is implemented CDSC) containing

_j I

ATTACHMENT 1 (PAGE 1 OF 2)

EMERGENCY ACTION LEVEL (EAL) CRITERIA

.1 ELECTRICAL I

SECURITY Mode 5, 6 AOP-3B, Abnormal Shutdown Cooling, is implemented due to loss of ALL vital 4kV power supplies for GREATER THAN 15 minutes.

EA2 Mode 1, 2, 3, 4 Only ONE power source (off-site or diesel) is available to supply Unit I (Unit 2) Sofety Related 4 kV buses for GREATER THAN 15 minutes AND the unit is Not on Shutdown (aoling (this is a condition where any additional single failure will result in Station Blackout).

EA3 Mode 1, 2 EOP-8, Functional Recovery Procedure, is implemented on loss of 125 Volt DC bus TAI

'Security Emergency' or 'Security Alert' Declared for

• Intrusion into the plant Protected Area

• Sabotage inside the plant Protected Area I1 1.

2.

3.

4.

EUI Loss of ALL off-site 500 kV AND 69kV/1 3kV SMECO power to both 4 kV safety related buses on either unit AND at least one off-site source is not restored to a bus within 15 minutes.

EU2 AOP-7J, Loss of 120 Volt Vital AC or 125 Volt Vital DC Power, is implemented AND 125 Volt DC power is lost for GREATER THAN 15 minutes.

TUl

1. 'Security Emergency" or 'Security Alert" Declared for attempted intrusion into the plant Protected Area.

2. 'Security Event' declared for:

• Sabotage within or to ISFSI Protected Area

• Intrusion into ISFSI Protected Area 1W Fir Cor det I _-

F-FIRE Areas of Concern for Safe Shutdown NATURAL PHENOMENA

• Containment

• Turbine Building

• Intake Structure

• Diesel Generator Building

• Main Station & Service Station Transformer

• 13kV Switchgeor Houses

• 13kV Voltage Regulators

• PWST11/12

• RWIT11/21

• CST11/12/21

• Fast 11/21

• 69 EL Auxiliary Building Electrical Rooms

• Control Room HVAC Room

• RWT Rooms

• Diesel Generator Rooms

• Electrical Penetration Rooms

• RCS Sampling Rooms

.
1 -1

j

~j;,,47,Oj.I

.,:?.

i '

S D' :'

IAI

1. AOP-9 Series procedure implemented for fire.

2. Fire in an Area of Concern for Safe Shutdown that is not extinguished within 30 minutes of its detection.

3. Fire in an Area of Concern for Safe Shutdown that is not extinguished within 15 minutes of the first extinguishing agent being applied.

4. Explosion in ANY of the below listed areas:

• ANY area listed in the entry section of an AOP-9 series procedures.

• ANY Area of Concern for Safe Shutdown.

NA]

1. Seismic event causing ground acceleration GREATER THAN 0.089 horizontal or 0.053g vertical.

2. Sustained wind speed GREATER THAN 90 MPH (40 meters/second) for AT LEAST 15 m

3. Observable damage to equipment located inside an Area of Concern for Safe Shutdowr

4. Damage to RWT 11 (21) or PWST 11 (12) that in the SEC's judgment is significant.

5. Bay water level at or above the top of the traveling screen cover housing.

6. Bay water level is AT LEAST 6 feet below mean sea level.

\\~--r I

Jlored for attempted 11 Fire in/involving any of the below listed areas, that is not extinguished within 15 minutes of Control Room notification or receipt of a 1 (24B, Fire System Control Panel, alarm for fire detection and fire suppression system actuation:

• Auxiliary Building

• Intake Structure

• Containment

• ISFSI Protected Area

• Containment Butler Building

• Main Station and Service Station

• Containment Emergency Air Lack Vestibule Transformers

• Diesel Generator Rooms

• North Service Building 12 Foot Elevation

• Diesel Generator Buildings (0C/lA)

• RWT Rooms

• Fire Pump House

• Turbine Building

• Fuel Oil Storage Tanks

• 13KV Switchgear Houses

• Hydrogen Storage Tanks

• 13KV Voltage Regulators nu 2.

3.

4.

5.

Earthquake detected by seismic instrumentation per 01-46 or based on Shift Manager judgment Tornado striking switchyard, plant Protected Area, or within the ISFSI Protected Area Sustained wind speed GREATER THAN 75 MPH (34 meters/second) for AT LEAST 15 m Bay water level at or above bottom of traveling screen cover housing Boy water level is AT LEAST 3.6 feet below mean sea level

'-'I

ERPIP 3.C REV. 26 i

'URAL PHENOMENA OTHER HAZARDS rceleratlon GREATER THAN 0.08g horizontal or 0.053g THAN 90 MPH (40 meters/second) for AT LEAST 15 minutes.

nt located inside an Area of Concern for Safe Shutdown.

iT 11 (12) that in the SEC's judgment is significant.

top of the traveling screen cover housing.

et below mean sea level.

OA1

1. Any condition which in the SEC's judgment indicates that safety systems may be degraded AND which requires emergency response organization staffing.

2. EOP-B, Functional Recovery Procedure, is implemented.

OA2 Toxic or flammable gas making an Area of Concern for Safe Shutdown inaccessible.

OA3

1. Observable damage to equipment located inside an Area of Concern for Sofe Shutdown caused by any of the following:

• Vehicle/VesselfAirplane crash

• Turbine failure generated missile

• Severe weather generated missile

• Explosion generated missile

• Flooding

2. Damage cused by any of the following to RWI-1 1 (21) or PIWST 11 (12) that in the SEC's judgment is significant

• Vehicle/Vessel/Airplane crash

• Turbine failure generated missile

• Severe weather generated missile

• Explosion generated missile

• Flooding 0A4 Control Room evacuation initiated per AOP-9A or AOP-1 1.

<3 instrumentation per 01.46 or based on Shift Manager nt Protected Area, or within the ISFSI Protected Area MHAN 75 MPH (34 meters/second) for AT LEAST 15 minutes Om of traveling screen cover housing feet below mean sea level OUI

1. Any condition which in the SEC's judgment indicates potential degradation in the level of safety of the plant.

0U2

1. On-site toxic or flammable gas release which in the Shift Manager's judgment could potentially degrade the level of safety of the plant OR affect the health of plant personnel.

2. Notification of a near-site release that may require evacuation of plant personnel OU3

1. Vessel crash into the Intake Structure Baffle Wall that in the SEC's judgment causes significant damage to the wall.

2. Vehicle crash into any of the below listed structures that in the SEC's judgment causes significant damage to the structure:

• 45 foot Switchgear Room

• Diesel Generator Rooms

• Diesel Generator Building (OQ1A)

• Vehicles carrying dry stored spent fuel

3. Aircraft Crash Into any of the below listed areas:

• Plant Protected Area

• Owner Controlled Area

• ISFSI Protected Area

4. Explosion within any of the below listed areas:

• Plant Protected Area

• ISFSI Protected Area

5. Turbine failure causing observable casing damage.

6. Flooding in an Area of Concern for Safe Shutdown that in the SEC's judgment is significant.

ERPI P-3.O IMMEDIATE ACTIONS Revision 27 Page 16 of 67 jj

.:j.........

A ATTACHMENT 3, INITIAL NOTIFICATION FORM USE THIS FORM FOR INITIAL NOTIFICATION AND EMERGENCY CLASS UPGRADING AND DOWNGRADING ONLY Form instructions are on back

1.

This is I is not an exercise. (circle one)

8.

Radioactivity:

2 Caller's Name:

O Has Not Been Released El Is Being Released:

El From The Plant El In The Plant

3.

Title/Organization: CCNPP 0

Has Been Released:

El From The Plant E In The Plant

4.

Facility: Calvert Cliffs Nuclear Power Plant

5.

Emergency Class:

E None

9.

Type of Release:

El None E Airborne El Unusual Event E Waterborne El Surface Spill El Alert

10.

Population Affected:

EL None El Yes El Site Emergency

11.

Protective Action Recommended (Choose one only):

El General Emergency El None

6.

Time Declared:

Date:

El Shelter entire 10 mile EPZ 7

Nature of Incident:

E None El Evacuate PAZ 1 unless conditions make evacuation dangerous and shelter Enter EAL Code

(

)

remainder of the 10 mile EPZ E

Evacuate PAZ 1 & 3 unless conditions make evacuation dangerous and Circle EAL Number shelter remainder of the 10 mile EPZ N/A 1

2 3

4 5

6 E

Evacuate PAZ 1 2, & 3 unless conditions make evacuation dangerous and shelter remainder of the 10 mile EPZ Enter two digit event code:

iD El Evacuate PAZ 1 & 2 unless conditions make evacuation dangerous and shelter remainder of the 10 mile EPZ

12.

This is / is not an exercise. (circle one)

13.

3 Time:

Date:

Printed Name & Signature

14.

Initial Notification completed by (circle one):

SM PGM S-NO SEC

15.

GIVE form to Communicator.

A Ma Us Ad 1; 1

1

.L5_

A.

NOTIFY agencies 1 through 5 below. GIVE items 1 through 12 above in order. Use conference feature on dedicated phone. IF conferencing feature is not available, THEN use (in order of preference): back-up (B/U) conference button on dedicated phone, individual buttons on dedicated phone, OR any outside line phone, OR radio.

B.

LOG time and name of receiving communicator and indicate the method used to transmit notification.

NOTE Maryland State Police receives calls for Maryland Emergency Management Agency until their offices are manned.

Maryland Department of the Environment Security receives calls for Maryland Department of the Environment until their offices are manned.

RECEIVED DEDICATED LOCATION TIME BY PHONE RADIO OUTSIDE LINE

1.

CALVERT (410-535-3491)

2.

ST. MARY'S (301-475-8016)

3.

DORCHESTER (410-228-2222)

4.

MEMA (or MSP)

(410-517-3600)

5.

MDE (410-631-3937)

• • NOTIFY the NRC immediately after the above agencies have been notified.**

6.

NRC I

I I

IN (301-816-5100)

C.

RECORD time all calls to above agencies were completed:

Time:

Date:

Pnnted Name & Signature FORWARD completed forms to Emergency Planning at event termination.

ERPIP-3.0 IMMEDIATE ACTIONS Revision 27 Pa.e 17 of 67 ATTACHMENT 3, INITIAL NOTIFICATION FORM FORM INSTRUCTIONS Page 2 of 2 Site Emergency Coordinator (or designee) completes items 1 through 12.

Items not mentioned are self-explanatory.

a.

Item 6:

COMPLETE this item last.

b.

Item 7:

RETRIEVE this information from the EAL chart in ERPIP-3.0, Immediate Actions, Attachment 1, Emergency Action Level (EAL) Criteria.

IF "None" (no emergency) is checked in Item 5, THEN CHECK 'None" after "Nature of Incident."

c.

Item 10:

IF General Emergency is checked in Item 5, THEN CHECK "Yes" (in Item 10, Population Affected).

IF General Emergency is not checked in, Item 5, THEN CHECK "NONE" (in Item 10, Population Affected).

d.

Item 11:

IF General Emergency is checked in Item 5, THEN DETERMINE appropriate Protective Action Recommendation and downwind zone(s) from ERPIP-3.0,, General Emergency Protective Action Recommendations, AND CHECK corresponding box (check one box only).

IF General Emergency is not checked in Item 5, THEN CHECK "NONE" (in Item 10, Population Affected).

e.

Site Emergency Coordinator must sign form after Items 1 through 12 have been completed.

2.

Communicator

a.

Provide the information in Items 1 through 12 from the top of the form to the agencies listed in the table provided on the form.

b.

Notify agencies 1 through 5 first (these are the State and local agencies).

Communication priorities are:

(1)

Conference button on Dedicated Offsite Agency phone.

(2)

B/U (back-up) conference button on Dedicated Offsite Agency phone.

(3)

Individual agency buttons on Dedicated Offsite Agency phone.

(4)

Any telephone.

(5)

The radio.

c.

Record time that agency answers and answering parties name. Check which method was used to transmit the notification.

d.

Communicator must sign form after completing notifications.

CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE NEOP-301-3(NEW)

TASK:

PURPOSE:

Verify Shutdown Margin for existing plant conditions (Mode, Tave, CEA Status) per NEOP 301 Evaluates an operator's ability to determine adequate shutdown margin, and to calculate the boric acid addition necessary to achieve it.

JOB PERFORMANCE MEASURE CALVERT CLIFFS NUCLEAR POWER PLANT LICENSED OPERATOR TRAINING Rev. 0

Page 2 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE NEOP-301-3 TASK:

Verify Shutdown Margin for existing plant conditions (Mode, Tave, CEA Status) per NEOP 301 PERFORMER'S NAME:

APPLICABILITY:

RO and SRO PREREQUISITES:

Completion of the knowledge requirement of the Initial License class training program for Nuclear Engineering Operating Procedures.

EVALUATION LOCATION:

PLANT SIMULATOR CONTROL ROOM EVALUATION METHOD:

ACTUAL PERFORMANCE DEMONSTRATE PERFORMANCE ESTIMATED TIME ACTUAL TIME TIME CRITICAL TASK:

TO COMPLETE JPM:

TO COMPLETE JPM:

15 MINUTES MINUTES NO TASK LEVEL:

LEVEL 1 TOOLS AND EQUIPMENT:

Blank copy of NEOP-301 Attachment 2 REFERENCE PROCEDURE(S):

NEOP-301 NEOP-23 TASK STANDARDS:

This JPM is complete when the required boric acid addition has been determined.

Page 3 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE NEOP-301-3 TASK:

Verify Shutdown Margin for existing plant conditions (Mode, Tave, CEA Status) per NEOP 301 DIRECTIONS TO EVALUATOR:

1.

Read the "Directions to Trainee" to the trainee.

2.

Note the time that the task is started. As the task proceeds, indicate completion of each element using the Standard criteria and the following notation:

- "S" for satisfactory completion

- "U" for unsatisfactory completion

- "N" if not observed OR not verifiable Critical elements must be observed or the evaluation is invalid.

3.

When the Terminating Cue is reached, tell the trainee that no further actions are necessary. Note the completion time.

4.

Document any instances of failure to comply with industrial safety practices, radiation safety practices and use of event free tools in the Notes area.

Immediately correct any actions that could result in violation of a safety procedure or personnel injury. NOTE: Violation of safety procedures will result in failure of the JPM.

5.

Questions to clarify actions taken should be asked after completion of the task.

6.

Indicate whether the task was completed satisfactorily on the basis of correct performance of all critical elements and completion of the task within the Estimated Time to Complete for Time Critical tasks.

7.

This JPM contains the steps, notes, cautions, and standards that are applicable to the initial conditions specified in this JPM. Steps that do not directly relate to this JPM, but appear in the procedure, are not listed here. It is the responsibility of the evaluator and/or observer to become familiar with the procedure prior to use of this JPM.

Page 4 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE NEOP-301-3 TASK:

Verify Shutdown Margin for existing plant conditions (Mode, Tave, CEA Status) per NEOP 301

8.

Document any instances of when the near miss threshold was reached due to inappropriate personnel actions/inactions or procedural quality as a result of the following:

Reactivity Management Unplanned power changes > 1%

Reduction of boron concentration of > 5% delta rho Radiation Safety Preventable PCIs Personnel Safety Operations near miss accident Reactor Safety Automatic trip near miss Actions required by operators to prevent an automatic trip Valid RPS trip or pre-trip alarms due to a plant transient Configuration Control Valve mispositioning or loss of control of tagging boundary resulting in loss of system inventory

Page 5 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE NEOP-301-3 TASK:

Verify Shutdown Margin for existing plant conditions (Mode, Tave, CEA Status) per NEOP 301 JPM STANDARDS (List of minimum Standard Practices for common evolutions at CCNPP)

If non-emergency condition, dispatches a P0 to verify pump is ready to be started.

Identify the Control Switch and Indicating Lights, using authonized identification.

Operate the Control Switch, to START, and check expected Indicating Light response.

Check proper pump operation (as applicable):

Motor amps Pump discharge pressure System flow Activation/Clearing of applicable Annunciators (e.g.; Hi Disch Press, Lo Hdr Press)

Identify the Control Switch and Indicating Lights, using authorized identification.

Operate the Control Switch, to STOP, and check expected Indicating Light response.

Check expected system response (e.g.; flow, pressure, level)

Identify the Control Switch and Indicating Lights, using authorized identification.

Select the Control Switch to the desired position.

Check Valve/Breaker position, using position Indicating Lights.

Check expected system response (e.g.; flow, pressure, level, volts, amps, KW)

Identify the Valve/Breaker Indicating Lights, using authorized identification.

Check the Valve/Breaker is in the correct position.

If Valve/Breaker is not in correct position, report Valve/Breaker position to CRS.

Identify the Valve/Breaker Indicating Lights, using authorized identification.

Check the Valve/Breaker is in the correct position.

If Valve/Breaker is not in correct position, operates Valve/Breaker to correct position.

Verify the following:

Suction Valve open Discharge Valve position (as applicable)

Miniflow Valve position (as applicable)

Pump and Motor oil levels are normal Adequate Suction Pressure Identify the Control Switch and Indicating Lights, using authorized identification.

Page 6 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE NEOP-301-3 TASK:

Verify Shutdown Margin for existing plant conditions (Mode, Tave, CEA Status) per NEOP 301 Operate the Control Switch, to START, and check expected Indicating Light response.

Check for proper Pump operation (as applicable):

Smooth, quiet operation consistent with pump history Oil level remains good Proper seal leakoff Proper discharge pressure Expected system flow Bgi a222 I,,

a MB22'>a22 2 :..

Identify the Control Switch and Indicating Lights, using authorized identification.

Operate the Control Switch, to STOP, and check expected Indicating Light response.

Check expected system response (e.g.; flow, pressure, level).

8.0 Operating a

1'vlimu.I 2

a

.a.a.a a

a..

Identify the Valve, using authorized identification.

Operate the Valve and check expected position indication change (e.g.; stem rise, pointer).

Check expected System response (e.g.; fluid flow sounds, pressure changes, tank levels).

Identify the Control Switch and Indicating Lights (if applicable), using authorized identification.

Operate the Control Switch and check expected Indicating Light response.

Check expected System response (e.g.; flow, pressure, levels, volts, amps).

gob ~~~~~..

.g gBB B..B BBB.

,1s w

AS22.2gg Identify the Valve/Breaker, using authorized identification.

Check the Valve/Breaker is in the correct position, using appropriate position indication (e.g.;

pointer, stem rise, flags, indicating lights).

If Valve/Breaker is not in correct position, report Valve/Breaker position to Control Room.

ggg~ g,2..

g gg g Identify the Valve/Breaker, using authorized identification.

Check the Valve/Breaker is in the correct position, using appropriate position indication (e.g.;

pointer, stem rise, flags, indicating lights).

If Valve/Breaker is not in correct position, operates Valve/Breaker to correct position.

Page 7 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE NEOP-301-3 ELEMENT STANDARD

(* = CRITICAL STEP)

TIME START Identify and locate OP-5 6.1.F ESTABLISH RCS boron concentration as follows:

CAUTION:

RCS boron concentration shall be maintained less than 2700 PPM in Mode 3 or 4 to comply with the design calculations used to determine trisodium phosphate volumes, [B0203]

1.

IF shutdown is for a refueling outage...

2.

OBTAIN the minimum RCS shutdown margin boron concentration for Modes 3,4 or 5, PER NEOP 301, OPERATOR SURVEILLANCE PROCEDURE (U-1)

Determines step is N/A Refers to NEOP-301 NEOP-13 Identify and locate NEOP-301.

Refer to NEOP-301 Table of Contents.

Same as element.

Determines the applicable step is 6. I.A 6.1.A MODES 3, 4 OR 5.(Figure Method)

1.

VERIFY AND DOCUMENT on within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of shutdown and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> that:

Determines completion of Attachment (2) is N/A at this time.

I CUE: If checked TAVE = 532 0F I

RCS average temperature (Tavg) is acceptable for current operating MODE.

Checks temperature is acceptable for MODE 3.

Page 8 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE NEOP-301-3 ELEMENT

(* = CRITICAL STEP)

STANDARD Refers to figure in NEOP-23 and determines required boron is 1654.9 (Unit 2 cycle 14).

OI-2B Refers to OI-2B to calculate boric acid addition Determines Step 6.1 is applicable CUE: 6.1 A initial conditions are met.

B. 1 DETERMINE the volume (gallons) of boric acid needed to achieve the desired RCS boron concentration or reactor power as follows:

~.

CACULAE te voume Refers to 01-2B Figure 1 or uses the usm~ ~e~.te~foi~wng:

OPS CALC program and calculates the required boric acid addition to be 3419 (+/-)150) gallons.

TI.E STOP TERMI1NATING CUE:

This JPM is complete when the required boric acid addition has been calculated. No further actions are required.

Page 9 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE NEOP-301-3 TASK:

Verify Shutdown Margin for existing plant conditions (Mode, Tave, CEA Status) per NEOP 301 Document below any instances of failure to comply with industrial safety practices, radiation safety practices and use of event free tools. NOTE: Violation of safety procedures will result in failure of the JPM.

NOTES:

DID A NEAR MISS OCCUR DUE TO INAPPROPRIATE PERSONNEL ACTIONS/iNACTIONS OR PROCEDURAL QUALITY?

YES (If yes, provide comments below)

NO COMMENTS:

The operator's performance was evaluated against the standards contained in this JPM and determined to be SATISFACTORY UNSATISFACTORY EVALUATOR'S SIGNATURE:

DATE:

CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE DIRECTIONS TO TRAINEE:

1.

To complete the task successfully, you must:

• perform each critical element correctly. You must inform the evaluator of the indications you are monitoring. Where necessary, consider the evaluator to be the CRS.

comply with industrial safety practices, radiation safety practices and use of event free tools. NOTE: Violations of safety procedures will result in failure of the JPM.

2.

Initial Conditions:

a.

Unit-2 was manually tripped two hours ago due to high RCP vibrations.

b.

Post trip actions have been completed per EOP-1 and OP-5 has been implemented.

c.

TAVE is 532oF

e.

Core Burnup is 8,000 MWD/ITU.

f.

RCS boron concentration is 1050 ppm.

g.

All CEAs are fully inserted.

h.

BAST concentration is 7.25%.

i.

You are performing the duties of the Unit-2 RO.

j.

The decision has been made to cool down to Mode 5 to inspect the RCP.

3.

Initiating Cue: The CRS directs you to calculate the amount of boric acid addition needed per OP-5 section 6. IF. Are there any questions? You may begin.

PLANT SHUTDOWN FROM HOT STANDBY TO COLD SHUTDOWN OP-S Rev. 46/Unit 1 Page 17 of 45 6.1 PREPARE FOR RCS COOLDOWN (Continued)

E.

IF needed, OBTAIN AND PLACE the respective key(s) in the following:

SGIS BLOCK A and B keyswitches

• SIAS BLOCK A and B keyswitches

• All four SIT OUT MOV keyswitches PORV 402 and 404 MPT Protection keyswitches F.

ESTABLISH RCS boron concentration as follows:

INIALS CAUTION RCS boron concentration shall be maintained less than 2700 PPM in Mode 3 or 4 to comply with the design calculations used to determine trisodium phosphate volumes.

[B0203]

1. IF shutdown is for a refueling outage, THEN OBTAIN from NFM the minimum shutdown margin boron concentration required for refueling.

2. OBTAIN the minimum RCS shutdown margin boron concentration for Modes 3,4 or 5, PER NEOP 301, OPERATOR SURVEILLANCE PROCEDURE (U-1).

NOTE

• The requirement to run an RCP and keep PZR spray in operation while borating is applicable at all times to ensure adequate mixing of the RCS inventory. [60271]

[10272]

Operating spray for at least 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after the shutdown boron concentration requirement has been verified will ensure proper RCS/PZR mixing. [60361]

3. IF NOT cooling down using natural circulation, THEN VERIFY that at least one RCP is running AND spray is in operation until the desired boron concentration has been REACHED AND VERIFIED. [60271] [B0272]

OP-5 Rev. 46/Unit 1 Page 18 of 45 PLANT SHUTDOWN FROM HOT STANDBY TO COLD SHUTDOWN

)

6.1.F PREPARE FOR RCS COOLDOWN (Continued)

INMALS NOTE An Operator involved in the cooldown and boration of the RCS, AND a Chemistry Technician should collaborate and decide on a sampling frequency based on the ability to develope a purposeful trend to ensure the correct boron concentration is achieved without exceeding 2700 PPM. Specific sampling frequency has not been established to allow flexibility in obtaining samples based on moving plant conditions.

4. CONTACT Plant Chemistry to commence periodic sampling of RCS boron to establish trending information AND to ensure the correct boron concentration is achieved without exceeding 2700 PPM. [B0605]

5. BORATE the RCS as necessary PER 01-2B, CVCS BORATION, DILUTION & MAKEUP OPERATIONS.

6. CONSIDER borating all the Purification lXs to SDM or the refueling boron concentration PER 01-2D, section titled, EQUALIZE THE PURIFICATION lXs TO THE SHUTDOWN BORON CONCENTRATION REQUIREMENT OR ECC BORON CONCENTRATION.

7. PRIOR to reducing RCS temperature less than 5150 F (as read on TI-1 12C OR TI-1 22C), VERIFY RCS boron is at shutdown margin boron concentration for Modes 3, 4 or 5, by chemical analysis. [B0270]1[B0599]

8. IF shutdown is for a refueling outage, THEN continue borating to refueling boron concentration while continuing on with this procedure.

--W-END Y

)

OPERATOR SURVEILLANCE PROCEDURE NEOP-301 Unit-1 and Unit-2 Rev. 4 Page 7 of 29 6.0 PERFORMANCE 6.1 SHUTDOWN MARGIN (AI CEAs Operable)

A.

MODE 3,4, or s( Figure Method)

1.

VERIFY AND DOCUMENT on Attachmnent 2 within four hours of shutdown

[8-13] and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> that:

RCS average temperature (Ta) is acceptable for currentoperating MODE A soluble boron concentration sample from the RCS has been obtained.

RCS soluble boron concentration Is greater than or equal to the Shutdown Boron Concentration required for the current bumup from Figure i-i.A3 of NEOP-13 (Figure 2-4lA.3 of NEOP-23).

2.

INSTRUCT a SRO to independently review the information in Attachment 2.

3.

IF the RCS soluble boron concentration Is less than the required shutdown boron concentration for the current burnup, THEN IMMEDIATELY START boration at greater than or equal to 40 gpm of boraled water at or above the higher of the concentrations beow 2300 ppm, or the required Shutdown Boron Concentration

4.

CONTINUE to borate until the RCS soluble Boron concentration is greater than or equal to the required Shutdown Boron Concentration.

B.

MODE 3. Tavg;5 215÷F

.ECC 50ppm. Method)

1.

CALCULATE a Shutdown Margin using Attachiment 3 and the steps below, AND DOCUMENT on Attachment 2 within tour hours of shutdown [B-13J and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, that the SHUTDOWN MARGIN is adequate. [B-I1]

a.

COMPLETE the previous critical conditions of Attachment 3.

1.

RECORD the unit and cycle numbers.

TECHNICAL DATA BOOK UNIT 2 NEOP-23/REV. 14 PAGE 23 OF 74 Sutdown Burnup Boron

( IMTU)

Mode 3 & 4 (ppm) 01951.4 100 1947.9 200 1944.4 300 1941.0 400 1937.5 500 1934.0 600 1930.5 700 1927.0 800 _

_1923.6 900 1920.1 1000 1916.6 1100

_1913.2 1200 T1909.7 1300 1906.2 1400 1902.7 1500 1899.3 1600 1895.8 1700 1892.3 1800 1888.8 1900 1885.4 2000 1881.9 2100 1878.4 2200 1874.9 2300 1871.4 2400 167.9 2500 1864.4 2600 1860.9 2700 1857.4 2800 15.

2900 1850.4 3000 18468 3100 1843.3 3200 1839.8 3300 1836.2 3400 183.7-3500 1829.1 3600 1825.5 3700 1822.0 3800 1818.4 3900 1814.8 4000 1811.2 4100 1807.6 4200 1803.9 4300 1800.3 4400 1796.7

=

4500 1793.0 4600 1789.3 4700 1785.6 4800 1782.0 4900 1778.2 5000 1774.5 5100 1770.8 5200 1767.0 5300 1763.3 5400 1759.5-FIGURE 2-Il.A.3 SHUTDOWN BORON CONCENTRATION vs. BURNUP ARI, NO XENON, EQUILIBRIUM SAMARIUM BORON-10 DEPLETION INCLUDED Unit 2 Cycle 14 (Page 2 of 3)

Shutdown t

Shutdown Boron Burnup Boron Mode 5 (MIMTU)

Mode 3 & 4 (ppm) j (ppm) 1883.

2263.7N-:

5500 1755.7 1879.2

--,2256-*

5600 1751.9 1875.4 t22556%'

5700 1748.1 1871.6 5800 1744.2 1867.8

-',',,kt224765v-5900 1740.4 1863.9 a.#G&2243A4A 6000 1736.5 1860.1 z

26100 1732.6 1856.3 R

'35.

6200 1728.7 1852.5 231.3-tNt 6300 1724.8 1848.7

-'222743zi 6400 1720.9 1844.9 Sv ~2223 O 6500 1716.9 1841.1

'.gf-W2219.34 6600 1712.9 1837.2 r..2215.2 6700 1708.9 1833.4 U

6800 1704.9 1829.6 2207,2at 6900 1700.8 1825.8 Eft'2203.'29"'

7000 1696.8 1822.0 21991 7100 1692.7 1T818.

'.i29.Ie 7200 1688.6 1814.3 g2191-1i3 7300 1684.5 1810.5 1-21874..

7400 1680.3 1806.6 ^.,--2183:0 7500 1676.1 1802.8 21-7819" 7600 1671.9 1798.9 1,

7414W 7700 1667.7 1795.1

-42170.184W 7800 1663.5 1791.2 4A 2 166:8Mz 7900 1659.2 1787.4 W

12i62.M78, 8000 1654.9 1783.5 iti4A2158.7j.

8100 1650.6 1779.7

- 2154'6-8200 1646.2 1775.8 k-2150.5'.;

8300 1641.8 1771.9

.2146.4X 8400 1637.4 1768.0 2142.32 8500 1633.0 1764.1

'2.138.2?-

8600 1628.6 1760.2 ~~21341 8700 1624.1 1756.3 i-2130.64W 8800 1619.6 1752.4 8900 1615.0 1748.4 2121 8V.

9000 1610.5 1744.5 iN4211I7J63; 9100 1605.8 1740.5 9200 1601.2 1736.6 921093iPi 9300 1596.6 1732.6 S"21 05. g 9400 1591.9 1728.6 5

101 e

9500 1587.1 1724.6 9600 1582.4 1720.6

,',2092 6 9700 1577.6 1716.6 20883 39 9800 1572.8 1712.6 2

9900 1568.0 1708.5

'+20793 10000 1563.1 1704.5 S

10100 1558.2 1700.4 A 2071 30 10200 1553.2 1696.3

'20671 10300 1548.3 1692.2

• 2062VW 10400 1543.3 1688.1 10500 1 538.3 1684.0

-'r2054'1%A 10600 1679.9 20498"-20410700 1528.1 1675.7 10800 1523.0 1671.5

.0 10900 1517.9 I

Shutdown Boron Mode 5 (ppm) rShutdown IBoron Modei I16 f6¢eSDMI (ppm) l I

16 b 7.3 1663.1 1658.9 1654.7 1650.4 1646.2 1641.9 1637.5 1633.2 1628.9 1624.5 1620.1 1615.7 1611.2 1606.8 l

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011-2B3 CVCS BORATION, DILUTION AND MAKEUP OPERATIONS Rev. 27 Page 9 of 61 6.0 SYSTEM OPERATION 6.1 BORATE MAKEUP MODE (CVCS) [B01541 [MEMORY USE A.

Initial Conditions

1.

Charging and Letdown are aligned for normal operation.

2.

CVCS makeup system aligned for manual operation.

3.

VCT Inlet, CVC-500-CV, handswitch HS-2500 in AUTO AND CVCS Diversion to Degas Isolation, CVC-325, locked open if a Volume Control Tank high level is anticipated.

4.

Space available in the Waste Processing System for CVCS Letdown effluent.

B.

Procedure NOTE When using a Direct Lineup, stop borating the RCS prior to the desire power level to allow flushing the boric acid from the line.

DETERMINE the volume (gallons) of boric acid needed to achieve the desired RCS boron concentration or reactor power as follows:

a. CALCULATE the volume using one of the following:

Formula on FIGURE 1 or FIGURE 2, BORATION VOLUME, depending on RCS temperature IBM personal computer program, BORATION OF THE RCS PROGRAM Review of the Boration/Dilution Log Reactivity Equivalency Plaques

b. PERFORM a peer check to verify the calculation for the volume of boric acid. [B02701

c. NOTIFY CRS of the boron addition.

2.

ADJUST CONC BORIC ACID FLOW CONTR, FIC-21 OY, to the desired flow rate.

3.

SET BA M/U BATCHING handswitch, FQIS-210Y, for the volume determined in Step 1.

PERFORM a peer check to verify the setting on FQIS-21 OY is correct.

OI-2B CVCS BORATION, DILUTION AND MAKEUP OPERATIONS Rev. 27 Page 1 of 1 BORATION VOLUME (GREATER THAN or EQUAL TO 5320 F)

NOTE Based on 7 1/4 % in BAST.

To convert BAST boron concentration from % to PPM, multiply the % by 1748.41.

~~~~~~~~~~..........................,.,_

~~~~...................,,_

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.*4 C;.)-;-\\

on

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i

>1k J

U at............

M "CIAt11-riL W

a.

a V (Y~dd GV) N011-V81 Na0)NO: N) 30W~H )

CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE NO-1-207(NEW)

TASK:

Valve Position Checklist PURPOSE:

Evaluates an Operator's Ability to Verify control Panel Switch Positions in Correct Lineup for Plant Conditions JOB PERFORMANCE MEASURE CALVERT CLIFFS NUCLEAR POWER PLANT LICENSED OPERATOR TRAINING Rev. 1

Page 2 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE NO-1-207 (NEW)

Valve position checklist TASK:

PERFORMER'S NAME:

APPLICABILITY:

RO and SRO PREREQUISITES:

Completion of the knowledge requirement of the Initial License class training program.

EVALUATION LOCATION:

PLANT SIMULATOR CONTROL ROOM EVALUATION METHOD:

ACTUAL PERFORMANCE ESTIMATED TIME ACTUAL TIME TO COMPLETE JPM:

TO COMPLETE JPM:

10 MINUTES MINUTES DEMONSTRATE PERFORMANCE TIME CRITICAL TASK:

NO TASK LEVEL:

LEVEL 1 TOOLS AND EQUIPMENT:

None REFERENCE PROCEDURE(S):

NO-1-207 Attachment 26 or 27 TASK STANDARDS:

This JPM is complete when all switch positions on I C08 and 9 have been verified per 6 of NO-1-207.

Page 3 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE NO-1-207 (NEW)

TASK:

Valve position checklist DIRECTIONS TO EVALUATOR:

NOTE TO EVALUATOR:

This JPMmay be performed on the Simulator or Unit 1 by using 6. It may be performed on Unit 2 using 7. If used on the actual plant, a walkdown is required beforehand to document the required changes to the evaluation tool to reflect plant conditions.

1.

Read the "Directions to Trainee" to the trainee.

2.

Note the time that the task is started. As the task proceeds, indicate completion of each element using the Standard criteria and the following notation:

- "S" for satisfactory completion

- "U" for unsatisfactory completion

- "N" if not observed OR not verifiable Critical elements must be observed or the evaluation is invalid.

3.

When the Terminating Cue is reached, tell the trainee that no further actions are necessary. Note the completion time.

4.

Document any instances of failure to comply with industrial safety practices, radiation safety practices and use of event free tools in the Notes area.

Immediately correct any actions that could result in violation of a safety procedures or personnel injury. NOTE: Violation of safety procedures will result in failure of the JPM.

5.

Questions to clarify actions taken should be asked after completion of the task.

6.

Indicate whether the task was completed satisfactorily on the basis of correct performance of all critical elements and completion of the task within the Estimated Time to Complete for Time Critical tasks.

7.

This JPM contains the steps, notes, cautions, and standards that are applicable to the initial conditions specified in this JPM. Steps that do not directly relate to this JPM, but appear in the procedure, are not listed here. It is the responsibility of the evaluator andlor observer to become familiar with the procedure prior to use of this JPM.

8.

Simulator Setup (if performed in the Simulator)

a.

IC-13 Unit 1 100%

b.

Use panel overrides to shut SI-622. Override the handswitch green light OFF and red light ON (prevents overpressurizing SIT)

Page 4 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE NO-1-207 (NEW)

TASK:

Valve position checklist

c.

Place locked valve deviation sheet in the Locked Valve book for pressurizing SITs. Ensure the locked valve book is placed where it is usually kept in the Control Room (desk top next to the electrical panels)

d.

Open SI-627 and place yellow caution tag on hand switch.

e.

Open SI-663 MOV.

9.

Document any instances of when the near miss threshold was reached due to inappropriate personnel actions/inactions or procedural quality as a result of the following:

Reactivity Management Unplanned power changes > 1%

Reduction of boron concentration of > 5% delta rho Radiation Safety Preventable PCIs Personnel Safety Operations near miss accident Reactor Safety Automatic trip near miss

• Actions required by operators to prevent an automatic trip

• Valid RPS trip or pre-trip alarms due to a plant transient Configuration Control Valve mispositioning or loss of control of tagging boundary resulting in loss of system inventory

Page 5 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE NO-1-207 (NEW)

TASK:

Valve position checklist JPM STANDARDS (List of minimum Standard Practices for common evolutions at CCNPP)

X -........- g > Ade If non-emergency condition, dispatches a PO to verify pump is ready to be started.

Identify the Control Switch and Indicating Lights, using authorized identification.

Operate the Control Switch, to START, and check expected Indicating Light response.

Check proper pump operation (as applicable):

Motor amps Pump discharge pressure System flow Activation/Clearing of applicable Annunciators (e.g.; Hi Disch Press, Lo Hdr Press)

Identify the Control Switch and Indicating Lights, using authorized identification.

Operate the Control Switch, to STOP, and check expected Indicating Light response.

Check expected system response (e.g.; flow, pressure, level)

Identify the Control Switch and Indicating Lights, using authorized identification.

Select the Control Switch to the desired position.

Check Valve/Breaker position, using position Indicating Lights.

Check expected system response (e.g.; flow, pressure, level, volts, amps, KW)

Identify the Valve/Breaker Indicating Lights, using authorized identification.

Check the Valve/Breaker is in the correct position.

If Valve/Breaker is not in correct position, report Valve/Breaker position to CRS.

so'~~~.

....Bes...... -

- - t Identify the Valve/Breaker Indicating Lights, using authorized identification.

Check the Valve/Breaker is in the correct position.

If Valve/Breaker is not in correct position, operates Valve/Breaker to correct position.

ss,

......... 2tg~s~

t.s

',g ss.

Verify the following:

Suction Valve open Discharge Valve position (as applicable)

Miniflow Valve position (as applicable)

Pump and Motor oil levels are normal Adequate Suction Pressure Identify the Control Switch and Indicating Lights, using authorized identification.

Operate the Control Switch, to START, and check expected Indicating Light response.

Page 6 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE NO-1-207 (NEW)

TASK:

Valve position checklist Check for proper Pump operation (as applicable):

Smooth, quiet operation consistent with pump history Oil level remains good Proper seal leakoff Proper discharge pressure Expected system flow lev

!g-x~~

Identify the Control Switch and Indicating Lights, using authorized identification.

Operate the Control Switch, to STOP, and check expected Indicating Light response.

Check expected system response (e.g.; flow, pressure, level).

840s Oa' ratg a 34iui V natv gesg Identify the Valve, using authorized identification.

Operate the Valve and check expected position indication change (e.g.; stem rise, pointer).

Check expected System response (e.g.; fluid flow sounds, pressure changes, tank levels).

9.0, Ioc......

ntrt V

'csNd4 VWidYI~s~~i~~e Identify the Control Switch and Indicating Lights (if applicable), using authorized identification.

Operate the Control Switch and check expected Indicating Light response.

Check expected System response (e.g.; flow, pressure, levels, volts, amps).

Locally checkin hj jBBB Identify the Valve/Breaker, using authorized identification.

Check the Valve/Breaker is in the correct position, using appropriate position indication (e.g.;

pointer, stem rise, flags, indicating lights).

If Valve/Breaker is not in correct position, report Valve/Breaker position to Control Room.

11.

La al

'aifin VicBkae pdid~ g#'2222gg

'B

'a a a a-aAarngaaaga aa Identify the Valve/Breaker, using authorized identification.

Check the Valve/Breaker is in the correct position, using appropriate position indication (e.g.;

pointer, stem rise, flags, indicating lights).

If Valve/Breaker is not in correct position, operates Valve/Breaker to correct position.

Page 7 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE NO-1-207 (NEW)

ELEMENT STANDARD

(* = CRITICAL STEP)

TIME START CUE: Begin with 1C08/1C09 (2C08/2C09)

Locate Attachment 26 (Unit-1) or 27 Same as element.

(Unit-2) of NO-1-207.

CUE: SI-622 is open. SI 627 is open and yellow tagged. SI-663 is open..

CUE: When questioned about the position of SI-622 respond that the CRO is pressurizing the Safety Injection Tank, the Outside Operator is checking the pressure of the Nitrogen system..

Ches ah3wth oiio Verifies each switch is aligned per the attachment. Verifies SI-627 is controlled via a tagout per NO 112, verifies SI-622 is controlled via an abnormal valve log entry per NO 205. Informs CRS that SI-663 is open, request permission to shut it and write an JR to document a mispositioning.

NOTE TO EVALUATOR:

Inability to locate handswitches or document any deviation to checklist positions constitutes a failure of the JPM.

TIME STOP TERMINATING CUE:

This JPM is complete when all switches on the appropriate attachment have been verified and documentation has been checked.. No further actions are required.

Page 8 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE NO-1-207 (NEW)

TASK:

Valve position checklist Document below any instances of failure to comply with industrial safety practices, radiation safety practices and use of event free tools. NOTE: Violation of safety procedures will result in failure of the JPM.

NOTES:

DID A NEAR MISS OCCUR DUE TO INAPPROPRIATE PERSONNEL ACTIONS/INACTIONS OR PROCEDURAL QUALITY?

YES (If yes, provide comments below)

COMMENTS:

NO The operator's performance was evaluated against the standards contained in this JPM and determined to be SATISFACTORY UNSATISFACTORY EVALUATOR'S SIGNATURE:

DATE:

CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE DIRECTIONS TO TRAINEE:

1.

To complete the task successfully, you must:

• perform each critical element correctly. You must inform the evaluator of the indications you are monitoring. Where necessary, consider the evaluator to be the CRS.

• comply with industrial safety practices, radiation safety practices and use of event free tools. NOTE: Violation of safety procedures will result in failure of the JPM.

2.

Initial Conditions:

a.

You are performing the duties of an extra CRO.

3.

Initiating Cue: You are to perform the Shift Turnover Switch and Valve Position Checklist. Are there any questions? You may begin.

Nuclear Operations Shift Turnover NO-1-207 Revision 32 Page 52 of 73 ATTACHMENT 26, SHIFT TURNOVER SWITCH AND VALVE POSITION CHECKLIST UNIT I CONTROL ROOM OPERATOR MODE 1-4 (Page 3 of 7) 1C08/1C09 (CONT) 1-HS-3615 1 lA LPSI HDR NORM/CLOSE (1) 1-HS-3625 1 lB LPSI HDR NORM/CLOSE (1) 1-HS-3635 12A LPSI HDR NORM/CLOSE (1) 1-HS-3645 12B LPSI HDR NORM/CLOSE (1) 1-HS-4150 11 CS HDR CLOSE (1) 1-HS-4151 12 CS HDR CLOSE (1) 1-HS5-3616 IIA MAIN BpSI DR, NORM/CLOSE (1) 1-HS-3617 11AAUXHPSI HR NORM/CLOSE (1) 1-HS-3626 1 lB MAIN HPSI HDR NORM/CLOSE (1) 1-HS-3627 1 lB AUX HPSI HDR NORM/CLOSE (1) 1-HS-3636 12A MAIN HPSI HDR NORM/CLOSE (1) 1-HS-3637 12A AUX HPS1 HDR NORM/CLOSE (1) 1-HS-3646 12B MAIN HPSI HDR NORM/CLOSE (1) 1-HS-3647 12B AUX HPSI HDR NORM/CLOSE (1) 1-HS-3663 11 SDC HX TO HPSI SUCT OFF/CLOSE (1) 1-HS-3662 12 SDC HX TO HPSI SUCT OFF/CLOSE (1) 1-HS-4144 I1 CNTMT SUMP DISCH CLOSE (1) 1-HS-301Y 12 HPSI PP PTL (2) 1-HS-301Z2 14 BUS DISC HPSI PP 13 CLOSED (2) 1-HIS-3653 I1SI HDR XCONN CLOSE (1) 1-HS-3658 SDC HX LPSI INL CLOSE/OFF (1) 1-HS-3657 SDC TEMP CONTR CLOSE (1) 1-HS-3652 SDC HDR RETURN ISOL OFF/CLOSE (1) 1-HS-3651 SDC HDR RETURN ISOL OFFICLOSE (1) 1-HS-4145 I1 CNTMT SUMP DISCH CLOSE (1)

(1)

(2)

Administratively controlled, verify listed position or verify control per NO-1-112 or NO-1-205.

Verif4 the listed position or verify control per NO-1-1 12 or CRS concurs abnormal position is correct for current plant conditions.

I

Nuclear Operations Shift Turnover Revision 32 Page 51 of 73 ATTACHMENT 26, SHIFT TURNOVER SWITCH AND VALVE POSITION CHECKLIST UNIT 1 CONTROL ROOM OPERATOR MODE 14 (Page 2 of 7) 1 C05/1C06 1 -HS-1402 1-HS-1403 I

1-HS-1404 1-HS5-1405 VALVE/

TCHIIESCR TJO CEDSCONTROLPANEL PORV 402 OVERRIDE PORV 402 BLOCK PORV 404 OVERRIDE PORV 404 BLOCK

. MNEC

~~~~~~~~~~~~~~~~~~~...........::::.

OFF (2)

AUTO/SHUT (2)

OFF/OPEN (1)

AUTO/SHUT (2)

OFF/OPEN (1) 4.

7

1C07 1 -HS-2517 I-HS-2518 1-HS-2519 1I-HS-2507 1-HS-269 1 -HS-2504 1-HS-2514 1-HS-2509 1 -HS-2508 1 C0811 C09 AUX SPRAY 12B3 LOOP CHG llIA LOOP CHG RCP BLEED-OFF RELIEF ISOL SI TO CHG 1HDR RWT CHG PP SUCT BA DIRECT M/U 11 BAST GRAVITY FD 12 BAST GRAVITY FD LOCKED CLOSE (1)

OPEN (1)

OPEN (1)

LOCK13D OPEN (1)

OFF/CLOSE (1)

AUTO/CLOSE (1)

AUTO/CLOSE(1)

AUTO/CLOSE(1)

AUTO/CLOSE (1)

(1)

(2)

Administratively controlled, verify listed position or verify control per NO-1-1 12 or NO-1-205.

Verify the listed position or verify control per NO-1-112 or CRS concurs abnormal position is correct for current plant conditions.

I

ATTACHMENT 2, LOCKED VALVE DEVIATION SHEET UNIT:

CRS APPROVAL:

REASON FOR DEVIATION:

PRESSURIZE SIT(S) WITH NITROGEN ONE VALVE NUMBER Il-SI-612-CV I-SI-622-CV I-SI-632-CV lI-SI-642-CV VALVE DESCRIPTION 1I A SIT N2 SUPPLY I1I B SIT N2 SUPPLY I12A SIT N2 SUPPLY 12B SIT N2 SUPPLY VALVE PLACED OUT OF NORMAL POSITION DATE ABNORMAL CRO OPER TS FLOW DAE ANOMLINFORMED PE.

PATH SEC.

POSITION INn7LALS INIT l CHECK INrr.

INITALS OPEN N/A OPEN N/A OPEN N/A OPEN N/A VALVE RETURNED TO NORMAL POSITION NOML CR0 OPER SECOND CRS NORMAL INFORMED INIT.

CHECKER DATE INITIALS POSITION INITIALS (2) 1INITIALS (4)

(3)

CLOSE CLOSE CLOSE CLOSE I

R RO

_ I.

(1)

(2)

(3)

(4)

NOTES:

An individual sheet shall be used for each evolution involving locked valves.

The qualified operator restoring the valve to its "normal position" shall verify that the locking device is installed in a manner to prevent inadvertent operation of the locked valve, that the red, green or yellow tag is properly attached, that the locking device is not anchored to tubing, and two valves are not locked together using the same locking device, unless the valves are in series and are normally operated together.

The second checker must be a qualified operator; who shall independently verify that the valve is returned to its "normal posit:

as described above. The second check shall be completed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

The CRS initials on notification of the valve being returned to it's "normal position" and that the verification by the second cl 1HS3627 m*QfSI TR HP TES

~~FDA, NO-1-205, Revision 7

Calvert Cliffs Nuclear Power Plant ADMIN A2 Topics Tagging and Clearances Tagging and Clearances-Qualifications to pull Control Room panel fuses/slide links K/A 2.2.13 [3.6/3.8]

Question a:

What qualifications are required to pull control room panel fuses for a clearance and what qualifications are required for the verifier?

I I Satisfactory Unsatisfactory Candidate 1 of 4 ADMIN #2 Questions Safety tagging Revised 05/30/02

Calvert Cliffs Nuclear Power Plant ADMIN A2 Topics Tagging and Clearances Tagging and Clearances-Qualifications to pull Control Room panel fuses/slide links K/A 2.2.13 [3.6/3.81 Question a:

What qualifications are required to pull control room panel fuses for a clearance and what qualifications are required for the verifier?

Answer:

To be qualified to pull fuses or verify fuses pulled in control room panels, the person must be from the respective discipline (IM or EM) that operates the system/component.

(Operators are not qualified to pull or verify fuses in the control room panels).

Reference Use Allowed ? YES Reference 1: NO-1-112 Section 5.10.C.7 and 5.10.D.1 Comments:

[I~

1Satisfactory Unsatisfactory Candidate 2 of 4 ADMIN #2 Questions Safety tagging Revised 05/30/02

Calvert Cliffs Nuclear Power Plant ADMIN A2 Topics Tagging and Clearances Effects of tagging activities on Control Room Annunciators K/A 2.2.13 [3.6/3.8]

Question b:

11 Boric Acid Pump is being tagged out for maintenance. How wiln annunciator F-26, 11BA PUMP SIAS BLOCKED

• AUTO START be controlled?

Satisfactory Unsatisfactory Candidate 3 of 4 ADMIN #2 Questions Safety tagging Revised 05/30/02

Calvert Cliffs Nuclear Power Plant ADMIN A2 Topics Tagging and Clearances Effects of tagging activities on Control Room Annunciators K/A 2.2.13 [3.6/3.8]

Question b:

11 Boric Acid Pump is being tagged out for maintenance. How will annunciator F-26, 11BA PUMP

• SIAS BLOCKED

• AUTO START be controlled?

Answer:

1.

The annunciator card will be tagged out and a red dot will be applied to the window.

Reference Use Allowed? NO Reference 1 NO-1-112 Section 5.8.A.26 Comments:

Satisfactory l

ljUnsatisfactory Candidate 4 of 4 ADMIN #2 Questions Safety tagging Revised 05/30/02

NO-I-I 12 Safety Tagging Revision 20 Page 41 of 66 5.10.C Clearance Order Performance (Continued)

4.

For pressurized systems or components being removed from service, the Tagger shall verify that the system or component is adequately drained or depressurized where possible.

5.

For high-energy system restoration from a remote location, ensure that all personnel are clear from the immediate vicinity of the previous maintenance area, and that a checker is stationed to observe and report on system integrity following pressurization. This is only required for rapid system pressurization, and not for controlled restoration, such as warm-up of a main steam header following maintenance. [B05551

6.

The Tagger shall perform the Clearance order as written and initial the Clearance Order for the completed steps.

When using a real-time Clearance Order generated by STS, the Tagger is responsible for ensuring that it is the most recent revision of that Clearance Order. [B06451 For Clearance Items being restored, if the One-Tag process has determined that the Clearance Item's tag is to remain in the field for another existing Clearance, then that Clearance Item need not be checked by the Tagger.

7.

Specific EM/IM discipline components will be tagged by the respective discipline that is qualified t6 operate the system/component. These components include:

Ground Installation and Removal (EM) 13KV Components and above (EM)

SMECO components upstream of Breaker 252-2301 (EM)

Electrical/Instrument Components in tagouts involving ESFAS/RPS (IM)

Opening heat trace circuit breakers Pulling fuses inside Control Room Control Panels Operating all slide links Lifting and landing leads

8.

Notify a tagging verifier to perform an independent verification in accordance with this procedure. [B05521 [B04591

• If no verifications are required, then record the date and time that the Clearance Order was completed on the Clearance Order cover page (either manually on the Clearance Order or in STS).

Safety Tagging NO-i- 1 12 SRevision 20 Page 32 of 66 5.8.A Clearance Order Preparation (Continued)

26.

Annunciators shall be tagged at the actual Clearance boundary (e.g., at the alarm card or, annunciator module, not at the alarm window).

If a Control Room annunciation is caused by a Clearance for equipment that is being removed from service, a red dot shall be attached to the annunciator window and if compensatory action is required the Control Room shall list the action on the Shift Turnover Information Sheet.

Red dots applied and removed for this purpose should normally be removed and restored by Clearance Item instructional steps.

If a Control Room annunciator is specifically removed from service for maintenance on the annunciator or annunciator panel, but the equipment that is monitored by the annunciator is still in service, the annunciator shall be removed from service.

Appropriate compensatory actions shall be taken and documented on the Shift Turnover Information Sheet.

27.

When maintenance is performed on acid or caustic systems, system vents or drains should be tagged open to ensure positive isolation for personnel safety.

28.

When work is to be performed inside the main generator, steam generators, tanks, or components, asphyxiates shall be isolated from the confined space by the use of a blank flange, removal of a spool piece, a disconnected hose, or other measures deemed necessary by the S-WCU and the Shift Manager.

29.

When any RCS Loop Drain valve is tagged open, the Safety Tagging Office shall submit an IR to Mechanical Maintenance to torque shut the drain valve prior to Mode 2 in accordance with OP-6 Modes 1 & 2 Checklist.

B.

Process

1.

Clearance Orders may be used to:

Establish initial Clearance controls.

Change existing Clearance controls by adding or restoring individual Clearance Items, or by a combination of both.

Establish a test lineup of equipment/systems after maintenance has been completed (formerly a Test Record).

• Re-establish Clearance controls following an unsatisfactory test.

Perform the final restoration of Clearance controls.

2.

A Clearance Order shall not be created that is all instructions.

Instructional steps should typically be used to amplify or augment the equipment manipulations required to establish or restore Clearance controls (e.g. - "Ensure that the drain rate does not exceed the floor drain capacity in the next step." or "Contact the Control Room prior to performing the next step.").

CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE ERPIP-3-8 (NEW)

TASK:

PURPOSE:

Respond to a Contaminated Injured Personnel Evaluates an Operator's ability to respond to an injured person in the RCA per the ERPIP.

JOB PERFORMANCE MEASURE CALVERT CLIFFS NUCLEAR POWER PLANT LICENSED OPERATOR TRAINING Rev. 2

Page 2 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE ERPIP-3-8 (NEW)

TASK:

Respond to a Contaminated Injured Personnel PERFORMERS NAME:

APPLICABILITY:

RO and SRO PREREQUISITES:

Completion of the knowledge requirement of the Initial License class training program for the Emergency Response Plan.

EVALUATION LOCATION:

PLANT SIMULATOR CONTROL ROOM EVALUATION METHOD:

ACTUAL PERFORMANCE DEMONSTRATE PERFORMANCE ESTIMATED TIME TO COMPLETE JPM:

ACTUAL TIME TO COMPLETE JPM:

TIME CRITICAL TASK:

10 MINUTES TASK LEVEL:

LEVEL 1 TOOLS AND EQUIPMENT:

MINUTES NO Working copies of ERPIP 3.0, Attachment 15 REFERENCE PROCEDURE(S):

Immediate Actions ERPIP 3.0, Attachment 15 TASK STANDARDS:

This JPM is complete when determination is made to place an alerting call to Calvert Memorial Hospital that they will receive a contaminated injured person.

Rev. 2

Page 3 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE ERPIP-3-8 (NEW)

TASK:

Respond to a Contaminated Injured Personnel DIRECTIONS TO EVALUATOR:

1.

Read the "Directions to Trainee" to the trainee.

2.

Note the time that the task is started. As the task proceeds, indicate completion of each element using the Standard criteria and the following notation:

- "S" for satisfactory completion

- "U" for unsatisfactory completion

- "N" if not observed OR not verifiable Critical elements must be observed or the evaluation is invalid.

3.

When the Terminating Cue is reached, tell the trainee that no further actions are necessary. Note the completion time.

4.

Document any instances of failure to comply with industrial safety practices, radiation safety practices and use of event free tools in the Notes area.

Immediately correct any actions that could result in violation of a safety procedure or personnel injury. NOTE: Violation of safety procedures will result in failure of the JPM.

5.

Questions should be asked after completion of the task.

6.

Indicate whether the task was completed satisfactorily on the basis of correct performance of all critical elements and completion of the task within the Estimated Time to Complete for Time Critical tasks.

7.

This JPM contains the steps, notes, cautions, and standards that are applicable to the initial conditions specified in this JPM. Steps that do not directly relate to this JPM, but appear in the procedure, are not listed here. It is the responsibility of the evaluator and/or observer to become familiar with the procedure prior to use of this JPM.

8.

Simulator Setup:

Rev. 2

Page 4 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE ERPIP-3-8 (NEW)

TASK:

Respond to a Contaminated Injured Personnel

9.

Document any instances of when the near miss threshold was reached due to inappropriate personnel actions/inactions or procedural quality as a result of the following:

Reactivity Management Unplanned power changes > 1%

Reduction of boron concentration of > 5% delta rho Radiation Safety Preventable PCIs Personnel Safety Operations near miss accident Reactor Safety Automatic trip near miss Actions required by operators to prevent an automatic trip Valid RPS trip or pre-trip alarms due to a plant transient Configuration Control Valve mispositioning or loss of control of tagging boundary resulting in loss of system inventory Rev. 2

Page 5 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE ERP[P-3-8 (NEW)

TASK:

Respond to a Contaminated Injured Personnel JPM STANDARDS (List of minimum Standard Practices for common evolutions at CCNPP)

S g

a.. p,

.Mapa If non-emergency condition, dispatches a PO to verify pump is ready to be started.

Identify the Control Switch and Indicating Lights, using authorized identification.

Operate the Control Switch, to START, and check expected Indicating Light response.

Check proper pump operation (as applicable):

Motor amps Pump discharge pressure System flow Activation/Clearing of applicable Annunciators (e.g.; Hi Disch Press, Lo Hdr Press) 2...............

S o

g Identify the Control Switch and Indicating Lights, using authorized identification.

Operate the Control Switch, to STOP, and check expected Indicating Light response.

Check expected system response (e.g.; flow, pressure, level)

Identify the Control Switch and Indicating Lights, using authorized identification.

Select the Control Switch to the desired position.

Check Valve/Breaker position, using position Indicating Lights.

Check expected system response (e.g.; flow, pressure, level, volts, amps, KW)

Identify the Valve/Breaker Indicating Lights, using authorized identification.

Check the Valve/Breaker is in the correct position.

Sa2aH

......a2~~ss Ba 22a.a c

fVav/Beae is not i coretpositon reotaveBeke.osto to. CR.

0 Verifyig vavhree pol ehifo Valv.poitin.(a.aplicble Identify the Control Switch and Indicating Lights, using authorized identification.

Cehect the Control Switchv i the SRiredc position.

IfeckValve/Breakeri nostioncorrect poosition, opercatesnVaLveBrakrtos oretpsiin Check expca stediu ayspemrepone(~. lw rsue eevls ms W

M-SutoMaleoe Identify the Conte/rolSithandr Indicating Lights, using authorized identification.

Operatef the Conte/rolaSitch IdtoiTATan ciheckuin expethoied idndctingfightirepose Rev. 2

Page 6 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE ERPIP-3-8 (NEW)

TASK:

Respond to a Contaminated Injured Personnel Check for proper Pump operation (as applicable):

Smooth, quiet operation consistent with pump history Oil level remains good Proper seal leakoff Proper discharge pressure Expected system flow U~.I to Localstpengpup Et-Identify the Control Switch and Indicating Lights, using authorized identification.

Operate the Control Switch, to STOP, and check expected Indicating Light response.

Check expected system response (e.g.; flow, pressure, level).

i...

Identify the Valve, using authorized identification.

Operate the Valve and check expected position indication change (e.g.; stem rise, pointer).

Check expected System response (e.g.; fluid flow sounds, pressure changes, tank levels).

9.0,.

Loc ala op.stin aote V 1asrW o60j~~c Vt Citi at~r less Identify the Control Switch and Indicating Lights (if applicable), using authorized identification.

Operate the Control Switch and check expected Indicating Light response.

Check expected System response (e.g.; flow, pressure, levels, volts, amps).

Lo..lly b e.i

.Br.....

Identify the Valve/Breaker, using authorized identification.

Check the Valve/Breaker is in the correct position, using appropriate position indication (e.g.;

pointer, stem rise, flags, indicating lights).

If Valve/Breaker is not in correct position, report Valve/Breaker position to Control Room.

.t.

L..o.ca.ll v

...ein Va f

k a

i a

Identify the Valve/Breaker, using authorized identification.

Check the Valve/Breaker is in the correct position, using appropriate position indication (e.g.;

pointer, stem rise, flags, indicating lights).

If Valve/Breaker is not in correct position, operates Valve/Breaker to correct position.

Rev. 2

Page 7 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE ERPIP-3-8 (NEW)

ELEMENT

(* = CRITICAL STEP)

STANDARD TIME START Locates ERPIP 3.0 Personnel Emergency tab ATTACHMENT 15 PERSONNEL EMERGENCY A.

OBTAIN PERSONNEL INFORMATION NOTE:

Conditions that warrant site attention and/or response may include, but are not limited to life threatening conditions such as severe bleeding, cardiac arrest, convulsions.

1.0 IF in the Shift Manager's/Control Room Supervisor's opinion the personnel emergency warrants site wide attention/response, THEN CONTINUE to Step C.

NOTIFY RESPONSE PERSONNEL.

Determines site wide response is necessary.

C.

DETERMINE APPROPRIATE RESPONSE Same as element Rev. 2

Page 8 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE ERPIP-3-8 (NEW)

ELEMENT

(* = CRITICAL STEP)

STANDARD Determines step is appropriate Announces location as Hot Machine Shop and profusely bleeding cut hand as nature of injury Determines step is appropriate Determines step is appropriate EPELA I Step 1. and I.v or I.

once.

4.0 CONFIRM First Aid Team response is in progress by contacting the FASR via radio.

D.

MONITOR RADIO COMMUNICATION [B-41 NOTE:

Headsets must be in cradle to hear over the speaker.

1.0 SELECT channel ID as primary channel on the CRS console.

Same as element 2.0 FASR should be on channel ID.

3.0 CRO should remain on channel 1H with volume turned up.

E.

DETERMINE CONTAMINATION AND HOSPITALIZATION STATUS CUE: Rad Safety Technician cannot determine if the individual is contaminated.

I 1.0 IF injured person is in a radiological controlled area, THEN REQUEST Radiation safety Technician to report contamination status.

Contacts First Aid Team or Radiation Safety Tech Consider the injured person contaminated Rev. 2

Page 9 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE ERPIP-3-8 (NEW)

ELEMENT

(* = CRITICAL STEP)

STANDARD NOTE:

If the First Aid Team Leader determines that hospital care is needed they will notify CAS/SAS to call for an ambulance.

CUE: The First Aid Team Leader has notified Security to call for an ambulance.

.rpireDetermines alerting call to hospital is infrd prso~iisc~tainaod~

HEN required.

TIME STOP TERMINATING CUE:

The JPM is complete when determination has been made to place I

the alerting call to hospital. No further actions are necessary.

Rev. 2

Page 10 CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE ERPIP-3-8 (NEW)

TASK:

Respond to a Contaminated Injured Personnel Document below any instances of failure to comply with industrial safety practice, radiation safety practices and use of event free tools. NOTE: Violation of safety procedures will result in failure of the JPM.

NOTES:

DID A NEAR MISS OCCUR DUE TO INAPPROPRIATE PERSONNEL ACTIONS/INACTIONS OR PROCEDURAL QUALITY?

YES (If yes, provide comments below)

COMMENTS:

NO The operator's performance was evaluated against the standards contained in this JPM and determined to be SATISFACTORY UNSATISFACTORY EVALUATOR'S SIGNATURE:

DATE:

Rev. 2

CCNPP LICENSED OPERATOR JOB PERFORMANCE MEASURE DIRECTIONS TO TRAINEE:

1.

To complete the task successfully, you must perform each critical element correctly. You must inform the evaluator of the indications you are moni-toring. Where necessary, consider the evaluator to be the CRS.

2.

Initial Conditions:

a.

Unit 1 and 2 are at 100% power.

b.

Unit 2 CRS is absent from the Control Room.

c.

Unit 1 has implemented AOP-2A for an RCS leak.

d.

You are an extra Control Room operator.

3.

Initiating Cue: A 911 call was taken by the CRS. He provides you with the following information and directs you to refer to ERPIP 3.0 Tab for Personnel Emergency and take the required action, while he deals with the AOP:

Injured person is in the Hot Machine Shop. Injury is a profusely bleeding cut hand. Call was made by Jim Turner.

Are there any questions? You may begin.

Rev. 2

IMMEDIATE ACTIONS ERPIP-3.0 Revision 27 Page 40 of 67 E,33. i i

3.Yk-g 11

'4* E M

'113 E

Ki qS3

......NO

.:3:,~33,--

ATTACHMENT 15, PERSONNEL EMERGENCY Page 1 of 3 1.0 Record the following information:

Callers Name:

Location of injured person:

e Nature of injury (brief description):

Date/time:

NOTE Conditions that warrant site attention and/or response may include, but are not limited to life threatening conditions such as severe bleeding, cardiac arrest, convulsions.

1.0 IF in the Shift Manager's/Control Room Supervisor's opinion the personnel emergency warrants site wide attention/response, THEN CONTINUE to Step C. NOTIFY RESPONSE PERSONNEL.

1.1 IF in the Shift Manager's/Control Room Supervisor's opinion the personnel emergency does not warrant site wide attention/response, THEN:

a.

CONTACT Fire & Safety Watch (FASW) Stander. IF the injured person is in a radiologically controlled area, THEN CONTACT a Radiation Safety Technician.

b.

INSTRUCT the FASW, and if called, the Radiation Safety Technician, to respond to the personnel emergency.

c.

EXIT this procedure.

d.

FORWARD this attachment to the Director - Emergency Planning.

IMMEDIATE ACTIONS ERPIP-3.0 Revision 27 MD_

_£ A I

m-2E O_

S0 i

ATTACHMENT 15, PERSONNEL EMERGENCY Page 2 of 3 SOUND the emergency alarm for 5 seconds.

2.0 IF injured person is in a radiological controlled area:

THEN ANNOUNCE "A personnel emergency exists." Give location and nature of injury. "First Aid Team and Radiation Safety Technician Respond."

3.0 REPEAT Step 1.0 and 2.0 or 2.1 once.

4.0 CONFIRM First Aid Team response is in progress by contacting the FASW via radio.

2.1 IF injured person is NOT in a radiological controlled area, THEN ANNOUNCE "A personnel emergency exists." Give location and nature of injury. "First Aid Team respond."

4.1 IF unable to contact the FASW by radio THEN USE the pager system as follows:

a.

On the telephone DIAL 6700

b.

ENTER ID number listed for Safety and Fire Protection on Operations turnover sheet.

c.

ENTER Control Room Telephone number l02-010 NOTE Headsets must be in cradle to hear over the speaker 1.0 SELECT channel 1 D as primary channel on the CRS console.

2.0 FASW should be on Channel 1D.

3.0 CRO should remain on channel IH with volume turned up.

ERPIP-3.0 IMMEDIATE ACTIONS Revision 27 Page 42 of 67 iP..

~~~~~~~~~~.

.......... :.:i..

';,zvD+<,,

ATTACHMENT 15, PERSONNEL EMERGENCY Page 3 of 3

A

D try"

! W I

TA

.....I.....I...

1.0 IF injured person is in a radiological controlled area, THEN REQUEST Radiation Safety Technician to report contamination status.

NOTE If the First Aid Team Leader determines that hospital care is needed they will notify CASISAS to call for an ambulance.

2.0 IF hospitalization is required and the injured person is contaminated, THEN PERFORM the following:

a.

INITIATE an alerting call to Calvert Memorial Hospital by dialing 8-1-410-535-4000 ext. 8344 or 8345.

b.

ENSURE you are speaking to a nurse or doctor and report the following:

Number of people_

Number contaminated_

Nature of injuries_

Estimated time of arrival 1.1 IF injured person is in a radiological controlled area AND the Radiation Safety Tech is unable to determine contamination status, THEN CONSIDER the injured person contaminated.

2.1 IF either of the following conditions exist, THEN PROCEED to Step F. EVENT TERMINATION.

a.

Hospitalization is not required.

b.

Injured person is not contaminated.

c. & NOTIFY a Plant Health Physicist and-Radiation Safety Supervisor by any means possible (pager ID 405-2409 will page multiple Health Physicists and the Radiation Safety Supervisor simultaneously).

d.

REVIEW RM-1-101, Regulatory Reporting, reporting requirements es sss--

~

.~

z S.

[F. EVENT

.T i.:

M T...

I...

1.0 When notified by the first aid team that the event may be terminated, THEN:

RECORD the date/time:

l FORWARD this attachment to the Director-Emergency Planning.