ML061660368

Administrative Documents

ML061660368
Person / Time
Site:	Saint Lucie
Issue date:	12/21/2004
From:	NRC/RGN-II
To:
References
50-335/04-302, 50-389/04-302
Download: ML061660368 (180)

Text

Final Submittal (Blue Paper)

ST. LUCIE RETAKE EXAM 05000335/2004302 & 05000389/2004302 DECEMBER 21, 2004 FINAL JPMS & OUTLINE

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility:

Date of Examination:

Item Task Description Initials a

b-c#

1.

a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401.

VIA

,/0, W

R

b. Assess whether the outline was systematically and randomly prepared in accordance with I

Section D.1 of ES-401 and whether all K/A categories are appropriately sampled.

TT

c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.

N

d. Assess whether the justifications for deselected or rejected K/A statements are appropriate.

2.

a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, technical specifications, S

and major transients.

M

b. Assess whether there are enough scenario sets (and spares) to test the projected number U

and mix of applicants in accordance with the expected crew composition and rotation schedule L

without compromising exam integrity, and ensure that each applicant can be tested using A

at least one new or significantly modified scenario, that no scenarios are duplicated T

from the applicants' audit test(s), and that scenarios will not be repeated on subsequent days.

O0

c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative R

and quantitative criteria specified on Form ES-301-4 and described in Appendix D.

3.

a. Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2:

(1) the outline(s) contain(s) the required number of control room and in-plant tasks W

distributed among the safety functions as specified on the form

/

(2) task repetition from the last two NRC examinations is within the limits specified on the form T

(3) no tasks are duplicated from the applicants' audit test(s)

Olf, N

lo (4) the number of new or modified tasks meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on the form.

b Verify that the administrative outline meets the criteria specified on Form ES-301-1:

1) the tasks are distributed among the topics as specified on the form.-J 6I2) at least one task is new or significantly modified %'

(3) no more than one task is repeated from the last two NRC licensing examinations /

c. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days.

4.

a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections.

G

b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.

i_

?

N

c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5.

E

d. Check for duplication and overlap among exam sections.

NA A

e. Check the entire exam for balance of coverage.

f. Assess whether the exam fits the appropriate job level (RO or SRO).

,,Printe Narge/Si reDate

a. Author sl S.1.

Lo,7IAv*ev

JLA,

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b. Facility Reviewer(*)

t 14 u t,

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c. NRC Chief Examiner(#)

Ae. //

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d. NRC Supervisor

//

/

CV.

Note:

1. Independent NRC reviewer initial items in Column 'c"; chief examiner concurrence required.

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CVVJ AJ-i)C Cl-/Vf~ly /

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ES-201, Page 25 of 27

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ES-301 Administrative Topics Outline Form ES-301-1 Facility:

Saint Lucie Date of Examination: 12-21-04 Examination Level (circle one): RO(SR_

Operating Test Number:

Administrative Topic Type Describe activity to be performed-(see Note)

Code*

Conduct of Operations FCV-26-2 Fails Open, apply Tech Specs 2.1.12 N

Conduct of Operations N

Use Control Wiring Diagrams 2.1.24 Equipment Control N

2.2.26 Refueling Administrative Requirements Radiation Control N

Release 1 B Waste Monitor Tank 2.3.6 Emergency Plan N

Loss of Control Room Annunicators 2.4.32 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

• Type Codes & Criteria:

(C)ontrol room (D)irect from bank (.L 3 for ROs; <4 for SROs & RO retakes)

(N)ew or (M)odified form bank L> 1)

(P)revious 2 exams L< 1; randomly selected)

(S)imulator ES-301, Page 22 of 27

ES-301 Operating Test Quality Checklist Form ES-301-3 Facility:

I"'

L F,

oL Date of Examination: !a1/j.5-d-/4 rating TestNumber:

Initials

a.

General Criteria b-c#

a.

The operating test conforms with the previously approved outline; changes are consistent with

_W 11 sampling requirements (e.g., 10 CFR 55.45, operational im ortance, safet function distribution).

b.

There is no day-to-day repetition between this and other operating tests to be administered N

'/"

T durinn this examination.

C.

The operating test shall not duplicate items from the applicants' audit testis). (see Section D.1.a.)

d.

Overlap with the written examination and between different parts of the operating test is within W/A -4 acceptable limits.I

ý

e.

It appears that the operating test will differentiate between competent and less-than-competent applicants at the designated license level.

2. Walk-Through Criteria

a.

Each JPM includes the following, as applicable:

initial conditions initiating cues references and tools, including associated procedures reasonable and validated time limits (average time allowed for completion) and specific designation if deemed to be time-critical by the facility licensee operationally important specific performance criteria that include:

detailed expected actions with exact criteria and nomenclature system response and other examiner cues statements describing important observations to be made by the applicant criteria for successful completion of the task identification of critical steps and their associated performance standards restrictions on the sequence of steps, if applicable

b.

Ensure that any changes from the previously approved systems and administrative walk-through outlines (Forms ES-301-1 and 2) have not caused the test to deviate from any of the acceptance A.,

criteria (e.g., item distribution, bank use, repetition from the last 2 NRC examinations) specified on those forms and Form ES-201-2.

3. Simulator Criteria The associated simulator operating tests (scenario sets) have been reviewed in accordance with j4 4 Form ES-301-4 and a copy is attached.

Printed Name I Signature Date

a.

Author ROXAl*

T-

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JW N

7_1 -

b.

Facility Reviewer()

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c.

NRC Chief Examiner (#)

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d.

NRC Supervisor

_z 1 4V NOTE:

The facility signature is not applicable for NRC-developed tests.

Independent NRC reviewer initial items in Column 'c"; chief examiner concurrence required.

ES-301, Page 24 of 27

REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM APPLY APPLICABLE TECH SPECS - UNIT 1 CANDIDATE EXAMINER

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM APPLY APPLICABLE TECHNICAL SPECIFICATIONS UNIT 1 KA Statement:

Ability to apply technical specifications for a system.

KA #:

2.1.12 (2.9 / 4.0)

References:

OP-1-0010125A, Surveillance Data Sheets OPS-503, Operations Department Policy, Tech Spec Guidance ADM-68.01, Containment Leakage Rate Testing Program U2 FSAR Table 6.3-52 and Design Bases Unit 1 Technical Specifications Candidate:

Name Time Start Time Finish Performance Rating:

Sat Unsat Validation Time 15 minutes Examiner:

Comments Signature:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 2

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM APPLY APPLICABLE TECHNICAL SPECIFICATIONS UNIT I Directions to the candidate for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference normally available in the Control Room to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions Unit 1 is at approximately 100% power. While stroke testing was being performed it is determined that FCV-26-5, Isolation Valve (Penetration P-25C) for Containment Air Radiation Monitor Common Return, will not close. E/M has determined that the valve will take at least 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to repair.

Initiating Cue You are the Unit Supervisor. You are tasked to determine which Technical Specifications are applicable.

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 3

START TIME:

Consult OPS-503, Operations Department Policy, Technical Specification Guidance 3 /

4.6.3 Containment Isolation Valves.

1. Any valve on a line that penetrates the containment may be a containment isolation valve.

STEP 1:

A. To determine if it is a containment isolation valve reference ADM-68.01, Containment Leakage Rate Testing Program, Unit #1 UFSAR table 6.2-16 and Unit #2 tables 6.2-52 & 53.

SAT UNSAT STANDARD:

DETERMINE FCV-26-5 is listed in Table 1 Unit 1 Containment Isolation Valves.

COMMENTS:

V6565 isolates return flow from the Containment Air Monitoring System back to Containment. (Drawing 8770-G-092)

.4 STEP 2: If the valve in question is listed in ADM-68.01, then apply Tech Spec 3.6.3.1.

STANDARD:

APPLY Tech Spec 3.6.3.1 COMMENTS:

SAT UNSAT I ______________________

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 4

T STEP 3: 3.6.3.1 The containment isolation valves shall be OPERABLE:

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With one or more of the isolation valve(s) inoperable, either:

a. Restore the inoperable valve(s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or

b. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or

c. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange; or

d. Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

CRITICAL STEP SAT UNSAT STANDARD:

ACTION

b. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position.

(Remove power to FCV-26-6 solenoid, preferred) or

c. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange.

COMMENTS:

4 Consult OPS-503, Operations Department Policy, Technical Specification Guidance 3 /

4.6.3 Containment Isolation Valves.

1. Any valve on a line that penetrates the containment may be a containment isolation valve.

STEP 4: G. For any inoperable containment isolation valve, consider any system Tech Specs that may apply.

SAT UNSAT STANDARD:

COMMENTS:

DETERMINE atmosphere radioactivity monitor is INOPERABLE Per T.S. 3.4.6.1 The following RCS leakage detection systems will be OPERABLE V6565 isolates return flow from the Containment Air Monitoring System back to Containment. (Drawing 8770-G-092)

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 5

T RCS Leakage Detection T.S. 3.4.6.1.b STEP 5:

With the required radioactivity monitor inoperable, analyze grab samples of the containment atmosphere or perform a RCS water inventory balance at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and restore the required radioactivity monitor to OPERABLE status within 30 days; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

STANDARD:

DETERMINE that an RCS inventory balance (DS #1) or grab samples need to be performed every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and restore the radioactivity monitor within 30 days.

EVALUATOR NOTE:

(Data Sheet #30, Unscheduled Surveillance and Evolutions Tracking would be filled out to track this)

CRITICAL STEP SAT UNSAT COMMENTS:

STEP (done):

Inform Candidate JPM is complete.

STANDARD:

SAT EXAMINER'S CUE:

THIS JPM IS COMPLETE.

COMMENTS:

UNSAT END OF TASK STOP TIME:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 6

CANDIDATE COPY (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Initial Conditions Unit I is at approximately 100% power. While stroke testing was being performed it is determined that FCV-26-5, Isolation Valve (Penetration P-25C) for Containment Air Radiation Monitor Common Return, will not close. E/M has determined that the valve will take at least 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to repair.

Initiating Cue You are the Unit Supervisor. You are tasked to determine which Technical Specifications are applicable.

ST. LUCIE PLANT OPS-503 OPERATIONS DEPARTMENT POLICY Rev.

10 Date 06/30/04 TECHNICAL SPECIFICATION GUIDANCE OPERATIONS DEPARTMENT Page 10 of 19 Operational Guidance for Section 3 / 4.6 3 /4.6.6.1 Shield Building Ventilation System When complying with action statement for Technical Specification 3.6.6.1 c the Spent Fuel Handling Machine is considered to have no load when no load is attached to the grapple.

With no load attached to the grapple the Spent Fuel Handling Machine May be operated over the Spent Fuel Pool.

3 / 4.6.3 Containment Isolation Valves NOTE The inoperable containment isolation valve may be used to provide containment isolation in order to comply with Tech Spec 3.6.3.1.

Containment penetration check valves are typically not found in the DBD.

Tech Spec 3.6.3.1 applies to all containment isolation check valves.

1.

Any valve on a line that penetrates the containment may be a containment isolation valve.

A.

To determine if it is a containment isolation valve reference ADM-68.01, Containment Leakage Rate Testing Program, Unit #1 UFSAR table 6.2-16 and Unit #2 tables 6.2-52 & 53.

B.

If the valve in question is listed in ADM-68.01, then apply Tech Spec 3.6.3.1.

C.

If the valve in question is determined to be a containment isolation valve, but not listed in ADM 68.01, then consult the DBD (Design Basis Documents) to determine its safety related function(s).

D.

If any one of the DBD safety related functions require the valve to be closed, then apply Tech Spec 3.6.3.1 Containment Isolation Valves.

E.

If all of the DBD safety related function(s) require the valve to be open, (for example: FCV-07-1A), then Tech Specs 3.6.1.1 and 3.6.3.1 are not applicable.

F.

If the valve is required to be closed by the DBD and/or Tech Spec 3.6.3.1 and needs to be opened for any reason, then apply Tech Spec 3.6.1.1 Containment Vessel Integrity and refer to ADM-25.04 Technical Specification Bases for required contingency actions.

G.

For any inoperable containment isolation valve, consider any system specific Tech Specs that may apply.

SCcL*

ST. LUCIE PLANT OPS-503 OPERATIONS DEPARTMENT POLICY Rev.

10 Date 06/30/04 TECHNICAL SPECIFICATION GUIDANCE OPE ATIONS rEPA NTMEr Page 11 of 19 Operational Guidance for Section 3 / 4.6 (continued) 3 / 4.6.3 Containment Isolation Valves (continued)

2.

If DC power is lost to SE-07-5A / B / C or D, Containment Pressure Transmitter Isolation Valves, the associated valve will fail open and can NOT be operated by the operator. Loss of power does not negatively impact the ability to maintain an intact containment pressure boundary. Therefore, these valves are not considered out of service.

3 / 4.6.5 Vacuum Relief Valves

1.

The Primary Containment Vessel to Annulus Vacuum Relief Valves are OPERABLE when the actuation setpoint is between 9.5 to 10.2 inches of water gauge differential. Activation within the setpoint range ensures both containment relief and containment isolation functions of these valves.

2.

If a primary containment vessel to annulus vacuum relief valve is inoperable, then Tech. Spec. 3.6.3 for one isolation valve inoperable and Tech. Spec. 3.6.5 for one primary containment vessel to annulus vacuum relief valve shall be entered simultaneously.

3.

Quarterly stroke testing of the Vacuum Relief valves in accordance with plant procedures does not render the valves inoperable. The open signal is momentary and does not prevent the vacuum reliefs from performing their design function.

3 /4.6.6.2 Shield Building Integrity

1.

Maintenance Hatch Seals A.

With one of the two hatch seals inoperable, the operability of the shield building can be maintained by closure of the manual isolation valve on the functioning seal.

B.

Closure of the manual isolation valve (V1 8263 / V1 8248) directly upstream of the supply check valve precludes an active failure of the check valve, but must be performed in accordance with AP 1/2-0010123, Administrative Control of Valves, Locks and Switches.

REVISION NO.:

PROCEDURE TITLE:

PAGE:

8A CONTAINMENT LEAKAGE RATE TESTING 22 of 32 PROCEDURE NO.:

PROGRAM ADM-68.01 ST. LUCIE PLANT TABLE 1 UNIT 1 CONTAINMENT ISOLATION VALVES (Page 2 of 2)

Valve Tag Number Penetration Function Testable Isolation Number During Time Plant (Sec)

Operation B. Manual or Remote Manual

1. V18794 8

Station air supply, Manual Yes NA V1 8796

2.

V-25-11,12 56 Hydrogen purge outside air make-up, Manual Yes NA (NC)

3.

V-25-13,14,15,16 57 & 58 Hydrogen purge exhaust, Manual (NC)

Yes NA

4.

V3463 41 Safety injection tank test line, Manual (NC)

Yes NA*

5.

V07009 41 Safety injection tank test line, Manual (NC)

Yes NA*

6.

V07206, V07189 46 Refueling cavity purification flow inlet, Manual Yes NA (NC)

7.

V07170, V07188 47 Refueling cavity purification flow outlet, Manual Yes NA (NC)

8.

FSE-27-1,2,3,4,8,11 48a & 48c Hydrogen sampling line, Remote manual Yes NA*

9.

FSE-27-5,6,7,9,10 51a & 51c Hydrogen sampling line, Remote manual Yes NA*

10. FCV-26-1 & 2 52a Radiation monitoring Yes NA

11. FCV-26-3 & 4 52b Radiation monitoring Yes NA

12. FCV-26-5 & 6 52c Radiation monitoring, return Yes NA

13. V00140 52d ILRT test tap Yes NA V00143

14. V00139 52e ILRT test tap Yes NA V00144

15. V00101 54 ILRT pressure connection Yes NA

16. FCV-03-1E & 1F 28 SI Tank Sample Yes NA**

NA-Manual Valve-Isolation time not applicable.

May be opened on an intermittent basis under administrative control.

Normally closed valves - Isolation time not applicable.

END OF TABLE 1

CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3.1 The containment isolation valves shall be OPERABLE:

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With one or more of the isolation valve(s) inoperable, either:

a.

Restore the inoperable valve(s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or

b.

Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or

c.

Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange; or

d.

Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.3.1.1 The isolation valves shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by performance of the cycling test, and verification of isolation time.

ST. LUCIE - UNIT 1 3/4 6-18 Amendment No. 90, 149

TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE

1.

AREA MONITORS APPLICABLE MODES ALARM SETPOINT

< 15 mR/hr

< 90 mR/hr

a. Fuel Storage Pool Area

b. Containment (CIS) 1 3

MEASUREMENT RANGE 10

- 104 mR/hr 1-105 mR/hr 1 - 107 R/hr ACTION 6

13 16 15

c. Containment Area - Hi Range

2.

PROCESS MONITORS

a. Containment

i. Gaseous Activity RCS Leakage Detection ii. Particulate Activity RCS Leakage Detection

b. Fuel Storage Pool Area Ventilation System

i.

Gaseous Activity ii. Particulate Activity 1

1,2,3, & 4

< 10 R/hr 1

1 1,2,3&4 1,2,3 &4 Not Applicable Not Applicable 10 -106 cpm 10-106 cpm 14 14 1

1

• • t 10 105 pCi/cc 1 - 106 cpm 12 12 With fuel in the storage pool or building.

With irradiated fuel in the storage pool or whenever there is fuel movement within the pool or crane operation with loads over the storage pool.

The Alarm Setpoints are determined and set in accordance with requirements of the Offsite Dose Calculation Manual.

ST. LUCIE - UNIT 1 3/4 3-22 Amendment No. 59, Q-3,134

TABLE 3.3-6 (Continued)

TABLE NOTATION ACTION 12 -

ACTION 13 -

ACTION 14 -

ACTION 15 -

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.12.

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

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

With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable Channel(s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or:

1)

Initiate the preplanned alternate method of monitoring the appropriate parameter(s), and

2)

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

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

ACTION 16 -

ST. LUCIE - UNIT 1 3/4 3-23 Amendment No. 59

REACTOR COOLANT SYSTEM 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.6.1 The following RCS leakage detection systems will be OPERABLE:

a.

The reactor cavity sump inlet flow monitoring system; and

b.

One containment atmosphere radioactivity monitor (gaseous or particulate).

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

a.

With the required reactor cavity sump inlet flow monitoring system inoperable, perform a RCS water inventory balance at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and restore the sump inlet flow monitoring system to OPERABLE status within 30 days; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

b.

With the required radioactivity monitor inoperable, analyze grab samples of the containment atmosphere or perform a RCS water inventory balance at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and restore the required radioactivity monitor to OPERABLE status within 30 days; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

c.

With all required monitors inoperable, enter LCO 3.0.3 immediately.

d.

The provisions of Specification 3.0.4 are not applicable if at least one of the required monitors is OPERABLE.

SURVEILLANCE REQUIREMENTS 4.4.6.1 The RCS leakage detection instruments shall be demonstrated OPERABLE by:

a.

Performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION of the required containment atmosphere radioactivity monitor at the frequencies specified in Table 4.3-3.

b.

Performance of the CHANNEL CALIBRATION of the required reactor cavity sump inlet flow monitoring system at least once per 18 months.

ST. LUCIE - UNIT 1 3/4 4-12 Amendment No. 144

REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM REFUELING ADMINISTRATIVE REQUIREMENTS CANDIDATE EXAMINER

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM REFUELING ADMINISTRATIVE REQUIREMENTS UNIT 1 KA Statement:

Knowledge of refueling administrative requirements.

KA#:

2.2.26 (2.5 / 3.7)

References:

- Plant Physics Curve Figure D.3

- AP 1-0010250, Guidelines for use of the Unit 1 High Density Spent Fuel Racks Candidate:

Name Time Start Time Finish Performance Rating:

Sat Unsat Validation Time 15 minutes Examiner:

Signature:

Comments ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 2

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM REFUELING ADMINISTRATIVE REQUIREMENTS UNIT I Directions to the candidate for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference normally available in the Control Room to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions Reactor Engineering has provided a Recommended Move List to move 2 fuel assemblies in the Unit 1 Spent Fuel Pool. All equipment to perform fuel movement in the Spent Fuel Pool is operable. All funnels have been verified in the correct positions and Nuclear Fuels has verified fuel burnup history is correct for fuel storage requirements.

Initiating Cue You are the Unit 1 Refueling Supervisor. Given the following Recommended Moves, determine if the moves are allowable.

RECOMMENDED MOVE LIST From To Step Assembly Insert Orient Core Bridge Trolley SFP NFS Upndr Core Bridge Trolly SFP 1

U48 I I

• I-I I

I I*-'--'i I

I R5 12 I

R53 205 FI nR I

I I

I I

I'~LI3I ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 3

START TIME:

STEP 1:

STANDARD:

Retrieves a controlled copy of Plant Physics Curve 0.3 Spent Fuel Map Retrieves a controlled copy of Plant Physics Curve D.3 Spent Fuel Map (Present Configuration) from the Control Room OBTAINS copy of Plant Physics Curve D.3.

SAT UNSAT EXAMINER'S NOTE: HAND STUDENT Plant Physics Curve D.3 Spent Fuel Map (Present Configuration) Page 1 of 2 COMMENTS:

STEP 2:

Obtains current revision of AP 1-0010250, Guidelines for use of the Unit 1 High Density Spent Fuel Racks STANDARD:

OBTAINS and VERIFIES current copy of procedure.

EXAMINER'S NOTE: HAND STUDENT AP 1-0010250, Guidelines for use of the Unit I High Density Spent Fuel Racks COMMENTS:

STEP 3:

Reviews Step 8.2 Rack Loading Restrictions STANDARD:

DETERMINES for move to R5, does meet >75% load restrictions and MOVE IS ALLOWABLE.

(60 non-restricted / 79 total assemblies = 75.9%)

COMMENTS:

SAT UNSAT CRITICAL STEP SAT

_UNSAT ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 4

STEP 4:

STANDARD:

Reviews Step 8.2 Rack Loading Restrictions DETERMINES for move to Q13, does NOT meet >75% load restrictions and MOVE IS NOT ALLOWABLE.

CRITICAL STEP SAT (45 non-restricted / 61 total assemblies = 73.8%)

UNSAT COMMENTS:

STEP (done):

Inform Candidate JPM is complete.

STANDARD:

SAT EXAMINER'S CUE:

THIS JPM IS COMPLETE.

COMMENTS:

UNSAT END OF TASK STOP TIME:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 5

CANDIDATE COPY (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Initial Conditions Reactor Engineering has provided a Recommended Move List to move 2 fuel assemblies in the Unit 1 Spent Fuel Pool. All equipment to perform fuel movement in the Spent Fuel Pool is operable. All funnels have been verified in the correct positions and Nuclear Fuels has verified fuel burnup history is correct for fuel storage requirements.

Initiating Cue You are the Unit 1 Refueling Supervisor. Given the following Recommended Moves, determine if the moves are allowable.

RECOMMENDED MOVE LIST From To Assembly Insert Orient Core Bridge Trolley SFP NFS Upndr Core Bridge Trolly SFP U48 L33 R5 2

R53 205 D28 Q13

Procedure No.

ST. LUCIE UNIT 1 1-0010250 ADMINISTRATIVE PROCEDURE Current Revision No.

5C F PL Effective Date SAFETY RELATED 10/26/04

Title:

GUIDELINES FOR USE OF THE UNIT I HIGH DENSITY SPENT FUEL RACKS Responsible Department: REACTOR ENGINEERING REVISION

SUMMARY

Revision 5C - Incorporated PCR 04-2964 to convert di Microsoft Word. (Helga Baranowsky, 10/18/04)

Revision 5B - Incorporated PCR 03-1056 to change A Revision 5A - Changed Fuel Resources to Nuclear Fu ocument from Word Perfect DOS 5.1 to F17 to AG17. (W. Mead, 04/16/03) els in Step 5.3. (Ray Klein, 05/07/99)

_________________________________ 4 Revision FRG Review Date Approved By Approval Date S 1 OPS 0

11/29/88 G. J. Boissy 01/30/89 DATE Plant General Manager DOCT PROCEDURE Revision FRG Review Date Approved By Approval Date DOCN 1-0010250 5C 02/24, 03/26/97 J. Scarola 03/26/97 SYS Plant General Manager COM COMPLETED N/A ITM 5C Designated Approver T. L. Patterson 10/18/04 Designated Approver (Minor Correction)

REVISION NO.:

PROCEDURE TITLE:

PAGE:

5C GUIDELINES FOR USE OF THE UNIT 1 HIGH 2 of 24 PROCEDURE NO.:

DENSITY SPENT FUEL RACKS 1-0010250 ST. LUCIE UNIT 1 TABLE OF CONTENTS SECTION PAGE 1.0 T IT L E......................................................................................................................

3 2.0 R EV IEW A N D A PPRO VA L.................................................................................

3 3.0 S C O P E...................................................................................................................

3 4.0 P R E C A U T IO N S..................................................................................................

5 5.0 R E S P O N S IB ILIT IE S............................................................................................

6 6.0 R E FE R E N C E S................................................................................................. 6 7.0 RECORDS AND NOTIFICATIONS.....................................................................

7 8.0 IN S T R U C T IO N S................................................................................................

8 8.1 F ue l F un ne ls..........................................................................................

.. 8 8.2 Rack Loading Restrictions.......................................................................

9 8.3 R ack Indexing System.............................................................................

10 8.4 Spent Fuel Pool Underwater Lighting...................................................... 11 8.5 Spent Fuel Funnel Handling Tool............................................................ 12 8.6 Boraflex Coupon Surveillance Program..................................................

13 FIGURES FIGURE 1 UNIT 1 HIGH DENSITY SPENT FUEL RACKS..................................... 14 FIGURE 2 INITIAL ENRICHMENT VS BURNUP REQUIREMENTS FOR REGION 2 SPENT FUEL STO RAG E.....................................................................

15 FIG U R E 3 R EG IO N 1 FU NN EL...............................................................................

16 FIG U R E 4 R EG IO N 2 FU NN EL...............................................................................

17 FIGURE 5 FUNNEL HANDLING TOOL GENERAL ARRANGEMENT DRAWING...... 18 FIGURE 6 BORAFLEX SURVEILLANCE COUPON AND COUPON ASSEMBLY...... 19 FIGURE 7 T-BAR LIGHT AND LOCATION OF T-BAR LIGHT HANGERS................. 20 FIGURE 8 TOP VIEW SHOWING ADJACENT CELLS BLOCKED BY FUNNELS...... 21 FIG U R E 9 IN D EX ING SYSTEM...............................................................................

22 FIGURE 10 FUNNEL HANDLING TOOL ALIGNMENT PLATE (CORRECT PO SITIO N O N FU NN EL)......................................................................

23 FIGURE 11 FUNNEL FULLY SEATED IN SPENT FUEL STORAGE RACK............. 24

REVISION NO.:

PROCEDURE TITLE:

PAGE:

5C GUIDELINES FOR USE OF THE UNIT 1 HIGH 3 of 24 PROCEDURE NO.:

DENSITY SPENT FUEL RACKS 1-0010250 ST. LUCIE UNIT 1 1.0 TITLE GUIDELINES FOR USE OF THE UNIT 1 HIGH DENSITY SPENT FUEL RACKS 2.0 REVIEW AND APPROVAL See cover page.

3.0 SCOPE 3.1 Purpose

1.

This procedure provides guidelines for use of the Unit 1 high density spent fuel racks and associated components and tools.

3.2 Discussion

1.

To ensure that sufficient spent fuel storage continues to exist at St. Lucie Unit 1, new high density storage racks have been installed. Each cell of the new spent fuel storage racks has an 8.65 inch (nominal) square cross-section, which will accommodate a single Combustion Engineering, Advanced Nuclear Fuels or equivalent fuel assembly, from either St. Lucie Unit 1 or Unit 2. A total of 1706 cells are arranged in seventeen distinct modules of various sizes and divided into two regions.

2.

The new position rack design allows for increased storage density of spent fuel.

3.

This procedure will provide guidelines for use of the racks and its associated components.

3.3 Authority

1.

This procedure implements plant guidelines intended to aid Operations in the use of the high density spent fuel racks and related components.

Operations will utilize this procedure with Reactor Engineering guidance.

REVISION NO.:

PROCEDURE TITLE:

PAGE:

5C GUIDELINES FOR USE OF THE UNIT 1 HIGH 4of24 PROCEDURE NO.:

DENSITY SPENT FUEL RACKS 1-0010250 ST. LUCIE UNIT 1 3.4 Definitions

1.

REGION 1 - Designed to store fuel assemblies with enrichments up to 4.5 wt. % U235 with no minimum burnup restrictions. Region 1 consists of racks Al, A2, B1 and B2. Region 1 contains 342 cells with a nominal center to center pitch of 10.12 inches. Figure 1 shows a plan view of Region 1.

2.

REGION 2 - Designed to store spent fuel assemblies with various initial enrichments which have accumulated the minimum acceptable burnups as required by Tech. Spec. Figure 5.6-1 (Figure 2 of this OP). Region 2 consists of racks C1, C2, C3, C4, D1, D2, D3, El, E2, F1, G1, G2 and H1 asshown in Figure 1. Region 2 contains 1364 cells with a nominal center to center spacing of 8.86 inches.

NOTE Region 1 funnels are not interchangeable with Region 2 funnels.

3.

REGION 1 FUNNEL - Provides lead-in guidance during insertion of a fuel assembly into a storage cell. The funnels are a duplex design as shown in Figure 3. Assemblies may be withdrawn through the duplex funnels without first removing the funnel. There are two variants of the Region 1 funnel.

Funnels for cells on the interior of a rack are identified by a solid square tab.

Funnels for cells on the periphery of a rack have a hole drilled through the square tab.

4.

REGION 2 FUNNEL - Provides lead-in guidance during insertion of a fuel assembly into a storage cell. The funnels are a duplex design as shown in Figure 4. Assemblies may be withdrawn through the duplex funnels without first removing the funnel.

5.

FUNNEL HANDLING TOOLS - The funnel handling tool is used to install and remove individual funnels. Region 1 and Region 2 have the specific funnel handling tools differing only in dimension (due to cell pitch difference between Region 1 and Region 2). The otherwise identical funnel handling tools are mechanically actuated, lightweight aluminum hand held tools designed for use by one individual from the spent fuel machine bridge (see Figure 5).

6.

BORAFLEX - Boraflex is a brand name silicone based polymer containing fine particles of boron carbide in homogeneous, stable matrix and is an integral part of every cell wall.

7.

POISON RACK DESIGN - Boraflex strips are sandwiched into the rack walls between the stainless steel plates to ensure K-effective remains below 0.95 in case flooding of the Spent Fuel Pool with pure unborated water occurs.

REVISION NO.:

PROCEDURE TITLE:

PAGE:

5C GUIDELINES FOR USE OF THE UNIT 1 HIGH 5 of 24 PROCEDURE NO.:

DENSITY SPENT FUEL RACKS 1-0010250 ST. LUCIE UNIT 1 3.4 Definitions (continued)

8.

SURVEILLANCE COUPON - 5 x 15 inch boraflex coupons attached to support assemblies (see Figure 6) and placed in rack cell locations as designated by separate procedure to track possible boraflex degradation.

9.

UNDERWATER LIGHTS - Moveable lights with handles which fit into corresponding hangers on the side of the spent fuel pool walls (see Figure 7).

4.0 PRECAUTIONS GENERAL NOTE Rack locations marked with an X on Figure 1 of this procedure shall be used to store Unit 1 fuel only until dispositioned by FPL Engineering to accept Unit 2 fuel or consolidation canisters. Rack locations AG17, AH17 marked with an * (asterisk) shall receive no fuel.

4.1 Prior to inserting a fuel assembly into a rack location, verification of the correct rack location via the rack indexing system, as well as the presence of a funnel (required on Region 2), shall be obtained by the spent fuel machine operator.

4.2 Fuel assemblies shall be inserted into Region 2 only into rack locations that have funnels in place. Fuel assemblies may be placed into Region 1 without funnels if the Region 1 funnels or tool is inoperable.

STORAGE REQUIREMENTS 4.3 Region 1 of the spent fuel storage racks can be used to store fuel which has a U-235 enrichment less than or equal to 4.5 weight percent. Region 2 can be used to store fuel which has achieved sufficient burnup such that storage in Region 1 is not required. The initial enrichment versus burnup requirements of Figure 5.6-1 of the Tech. Specs. and Figure 2 of this Administrative Procedure shall be met prior to storage of fuel assemblies in Region 2.

FUEL FUNNELS 4.4 Prior to fuel movement within the spent fuel pool, funnel placement needs shall be determined and satisfied.

4.5 The Region 1 and Region 2 funnels are not interchangeable. For details on funnel design and purpose see definitions 3.4.3 and 3.4.4.

REVISION NO.:

PROCEDURE TITLE:

PAGE:

5C GUIDELINES FOR USE OF THE UNIT 1 HIGH 6of24 PROCEDURE NO.:

DENSITY SPENT FUEL RACKS 1-0010250 ST. LUCIE UNIT 1 4.6 Funnels effectively block all cells adjacent to the locations for which they provide lead-in surfaces (see Figure 8). Fuel funnels cannot be placed side by side. A minimum clearance of one rack cell location is required between lead-in funnels.

5.0 RESPONSIBILITIES 5.1 The Operations Department is responsible for the administration and execution of this procedure.

5.2 Reactor Engineering is responsible for the determination of individual funnel locations prior to fuel movement in the spent fuel pool.

5.3 Nuclear Fuels will provide the burnup histories of spent fuel to determine the spent fuel storage requirements.

6.0 REFERENCES

NOTE One or more of the following symbols may be used in this procedure:

§ Indicates a Regulatory commitment made by Technical Specifications, Condition of License, Audit, LER, Bulletin, Operating Experience, License Renewal, etc. and shall NOT be revised without Facility Review Group review and Plant General Manager approval.

T Indicates a management directive, vendor recommendation, plant practice or other non-regulatory commitment that should NOT be revised without consultation with the plant staff.

T Indicates a step that requires a sign off on an attachment.

6.1 Technical Specifications Section 5.6 - Fuel Storage 6.2 Updated Final Safety Analysis Report (UFSAR)

Section 9.1.2.2.3 6.3 Procedures POP 3200090, Unit 1 Refueling Operation QI-5-PSL-1, Preparation, Revision, Review / Approval of Procedures 6.4 PCM-18-186, Spent Fuel Rerack

REVISION NO.:

5C PROCEDURE NO.:

1-0010250 PROCEDURE TITLE:

GUIDELINES FOR USE OF THE UNIT 1 HIGH DENSITY SPENT FUEL RACKS ST. LUCIE UNIT 1 6.5 6.6 6.7 6.8 PCM-142-186, Modifications to Support Rerack 1-LOI-RE-09, Unit 1 Boraflex Blackness Testing Technical Manual, HPS-1000/Q Lighting System Remote Ocean Systems, Inc JPN-PSL-SEFT-93-014, St. Lucie Unit 1 Safety Evaluation of Spent Fuel Pool (SFP) Coupon Surveillance Program 7.0 RECORDS AND NOTIFICATIONS 7.1 None

REVISION NO.:

PROCEDURE TITLE:

PAGE:

5C GUIDELINES FOR USE OF THE UNIT 1 HIGH 8of24 PROCEDURE NO.:

DENSITY SPENT FUEL RACKS 1-0010250 ST. LUCIE UNIT 1 8.0 INSTRUCTIONS CAUTION Prior to fuel movement, obtain the following information from Reactor Engineering:

A) Procedure Data Sheet(s) outlining desired fuel movement B) Region burnup requirements C) Individual funnel placements needed 8.1 Fuel Funnels

1.

Prior to inserting a fuel assembly into a rack cell location, visually verify that a lead-in funnel is in proper position over that location.

NOTE Fuel may be inserted into Region 1 rack cell locations without funnels since slight lead-in surfaces are built into the racks.

2.

Movement of individual funnels should be accomplished using the hand held tools described in Section 8.5.

NOTE For Region 1 there are two types of lead-in funnels. One type for interior cells of individual racks, the other for peripheral cells of individual racks.

Peripheral cell funnels have a hole drilled through the square identification tab.

3.

Fuel may be withdrawn through lead-in funnels, therefore funnels can be used as inspection funnels.

END OF SECTION 8.1

REVISION NO.:

PROCEDURE TITLE:

PAGE:

5C GUIDELINES FOR USE OF THE UNIT 1 HIGH 9 of 24 PROCEDURE NO.:

DENSITY SPENT FUEL RACKS 1-0010250 ST. LUCIE UNIT 1 8.2 Rack Loading Restrictions

1.

Loading racks El, E2 and G1 shall be accomplished as outlined below:

A.

Rack locations 17A through 17M, 18A through 18M of rack G1 and locations Q1 through Q16, R1 through R16, S1 through S16 of racks El and E2 are subject to the loading restrictions given below.

1.

Restricted locations of racks El, E2 and G1 shall not be filled unless 75% of the total fuel assemblies loaded into each individual rack are placed into the non-restricted locations first.

In support of this, loading rack G1 west to east and racks El and E2 south to north is recommended.

2.

No fuel shall be placed in locations AG17, AHl7.

• END OF SECTION 8.2

REVISION NO.:

PROCEDURE TITLE:

PAGE:

5C GUIDELINES FOR USE OF THE UNIT 1 HIGH 10 of 24 PROCEDURE NO.:

DENSITY SPENT FUEL RACKS 1-0010250 ST. LUCIE UNIT 1 8.3 Rack Indexing System NOTE The indexing system in a approximate indication of rack storage cell location. Final adjustments in fuel assembly position should be made by the SFM operator, if required, to ensure smooth fuel assembly insertion into the rack.

1.

Region 1 and Region 2 have separate indexing systems (see Figure 9).

Region 1 index numbers and letters are red on white and are pre-fixed by an X. Region 2 index numbers and letters are black on white.

END OF SECTION 8.3

REVISION NO.:

PROCEDURE TITLE:

PAGE:

5C GUIDELINES FOR USE OF THE UNIT 1 HIGH PROCEDURE NO.:

DENSITY SPENT FUEL RACKS 1-0010250 ST. LUCIE UNIT 1 8.4 Spent Fuel Pool Underwater Lighting

1.

The underwater lighting for the Unit 1 high density racks consists of hangers mounted to the spent fuel pool walls from which moveable underwater lights are hung. See Figure 7 for details on the hangers and underwater lights.

2.

Each light assembly consists of a single positionable reflector light and weighs approximately 70 lbs.

3.

Moving the underwater lights will be accomplished in the following manner:

A.

Notify Health Physics for support if pulling lights out of pool.

B.

Disconnect electrical cord from outlet.

C.

Lift the light up and out from hanger and move light to desired hanger.

D.

Re-connect electrical cord to closest outlet.

END OF SECTION 8.4

REVISION NO.:

PROCEDURE TITLE:

PAGE:

5C GUIDELINES FOR USE OF THE UNIT 1 HIGH 12 of 24 PROCEDURE NO.:

DENSITY SPENT FUEL RACKS 1-0010250 ST. LUCIE UNIT 1 8.5 Spent Fuel Funnel Handling Tool

1.

The funnel handling tools are designed for one man operation and is mechanically actuated. (See Figure 5, showing funnel handling tool design). Tool weighs about 45 lbs. Funnels weigh about 20 lbs. (Weights given are dry weights.)

2.

Funnels are moved in the following manner:

A.

Insert funnel tool into center plug on the duplex funnel. Ensure the tool alignment plate is positioned as shown in Figure 10.

B.

When the tool latches, a positive click will be felt as the tool seats.

C.

Pull up on the tool, observing the funnel to determine if the funnel is moving squarely out of its rack cell location. If not properly latched the funnel will tilt over to one side. To recover push down on the tool to latch both sides. Attempt to move the funnel again.

D.

Move funnel to its new location.

E.

Insert center plug into rack cell. Some side to side movement of the funnel may be necessary to get the chamfered plug to start into a cell. Insert funnel until fully seated as shown in side view, Figure 11.

F.

Pull up on the release bar and remove tool. Repeat Steps A to F for each desired funnel move.

END OF SECTION 8.5

REVISION NO.:

PROCEDURE TITLE:

PAGE:

5C GUIDELINES FOR USE OF THE UNIT 1 HIGH 13 of 24 PROCEDURE NO.:

DENSITY SPENT FUEL RACKS 1-0010250 ST. LUCIE UNIT 1 8.6 Boraflex Coupon Surveillance Program

1.

The inservice Boraflex Surveillance Program is part of FPL's commitment to the NRC to allow the reracking of the Unit 1 spent fuel pool. The Surveillance Program is intended to track and verify the integrity of the boraflex neutron absorber contained in the Region 1 and Region 2 high density racks. The Boraflex Surveillance Program consists of gamma dose determination to the boraflex and periodic blackness testing which replaced the Inservice Accelerated and Longterm Coupon Testing Program. Refer to reference 6.8.

END OF SECTION 8.6

REVISION NO.:

PROCEDURE TITLE:

PAGE:

5C GUIDELINES FOR USE OF THE UNIT 1 HIGH 15 of 24 PROCEDURE NO.:

DENSITY SPENT FUEL RACKS 1-0010250 ST. LUCIE UNIT 1 FIGURE 2 VS BURNUP REQUIREMENTS INITIAL ENRICHMENT FOR REGION 2 SPENT FUEL STORAGE (Page 1 of 1) 40 35 0

a-z Lu Lu Cd, 30 25 20 15 ACCEPrABLE/

BURNUP DOMAIN

/

/

UNACCEPTABLE BURNUP DOMAIN

//

//

~w I'l 10 5

n, U

1.5 2.0 2.5 3.0 3.5 4.0 4.5 INITIAL ENRICHMENT, WT % U-235 (P/AP/1-0010250IF2-RO)

REVISION NO.:

PROCEDURE TITLE:

PAGE:

5C GUIDELINES FOR USE OF THE UNIT 1 HIGH 16 of 24 PROCEDURE NO.:

DENSITY SPENT FUEL RACKS 1-0010250 ST. LUCIE UNIT 1 FIGURE 3 REGION 1 FUNNEL (Page 1 of 1)

Region 1 I.D. Tab

[f i

Hole in Identification Tab Peripheral Funnels Only Lead in Surface

\\

/

,,I I

Flush with Rack Surface Tension Center Springs Plug Plug Chamfer (PIAP/1-0010250/F3-RO)

REVISION NO.:

PROCEDURE TITLE:

PAGE:

5C GUIDELINES FOR USE OF THE UNIT 1 HIGH 17 of 24 PROCEDURE NO.:

DENSITY SPENT FUEL RACKS 1-0010250 ST. LUCIE UNIT 1 FIGURE 4 REGION 2 FUNNEL (Page 1 of 1)

Center Plug Lead in Surface

• I

[IllI Tension Springs i LI with urface F

FFlush Rack S Plug Chamfer (P/AP/1-0010250/F4-RO)

REVISION NO.:

PROCEDURE TITLE:

PAGE:

5C GUIDELINES FOR USE OF THE UNIT 1 HIGH 18 of 24 PROCEDURE NO.:

DENSITY SPENT FUEL RACKS 1-0010250 ST. LUCIE UNIT 1 FIGURE 5 FUNNEL HANDLING TOOL GENERAL ARRANGEMENT DRAWING (Page 1 of 1)

FUNNEL FUNNEL ALIGNMENT PLATE \\

COMPRESSION SPRINGS FLAPPER Z STOP PLATE CENTER PLUG LEAD IN (PIAP/1-0010250/F5-RO)

REVISION NO.:

PROCEDURE TITLE:

PAGE:

5C GUIDELINES FOR USE OF THE UNIT 1 HIGH 19 of 24 PROCEDURE NO.:

DENSITY SPENT FUEL RACKS 1-0010250 ST. LUCIE UNIT 1 FIGURE 6 BORAFLEX SURVEILLANCE COUPON AND COUPON ASSEMBLY (Page 1 of 1) 3/8 INCH HOLE 7/16 INCH TO CENTER t

5 X 15 TYP. POISON COUPON (P/API1-00 10250IF6-RO)

REVISION NO.:

PROCEDURE TITLE:

PAGE:

5C GUIDELINES FOR USE OF THE UNIT 1 HIGH 20 of 24 PROCEDURE NO.:

DENSITY SPENT FUEL RACKS 1-0010250 ST. LUCIE UNIT 1 FIGURE 7 LOCATION OF T-BAR LIGHT HANGERS T-BAR LIGHT AND (Page 1 of 1) 120 VAC CONNECTOR STAINLESS STEEL LIFT BAIL WITH STOP COLLAR TO PREVENT SLIPPING HP LIGHT-ING rj WET MATEABLE CONNECTORS WITH STAINLESS STEEL LOCKING RING WET MATEABLE CONNECTORS WITH STAINLESS STEEL LOCKING RING SYSTEM 7-BALLAST POWER SUPPLY IN SEALED STAINLESS STEEL HOUSING LOWER POLE MODULE REMOVEABLE LOW PRO OLLE F:

LIGT E

WET MATEABLE--

CONNECTORRELCO I

ADJUSTMENT T-BAR LIGHT HIGH PRESSURE HANGER DETAIL SODIUM LAMP I

pJ* 7-QUICK RELEASE ELECTRO-POLISHED K> 7 ~

REFLECTOR SIDE VIE W FRONT VIEW

,) K~'~

(P/A P/1-0010250/F7-RO)

REVISION NO.:

PROCEDURE TITLE:

PAGE:

5C GUIDELINES FOR USE OF THE UNIT I HIGH 21 of 24 PROCEDURE NO.:

DENSITY SPENT FUEL RACKS 1-0010250 ST. LUCIE UNIT 1 FIGURE 8 TOP VIEW SHOWING ADJACENT CELLS BLOCKED BY FUNNELS (Page 1 of 1)

Rack Cell Location Adjacent cell blocked by funnel lead-in surfaces (P/AP/1-0010250/F8-RO)

REVISION NO.:

PROCEDURE TITLE:

PAGE:

5C GUIDELINES FOR USE OF THE UNIT 1 HIGH 22 of 24 PROCEDURE NO.:

DENSITY SPENT FUEL RACKS 1-0010250 ST. LUCIE UNIT 1 FIGURE 9 INDEXING SYSTEM (Page 1 of 1)

...1...

re -' -x RPdr e q c--I 1

L e2*-t u 1 1-i *7 N uzn e 1 i -iy L -

-e t

1nc, Number ring W

i--e b3a c k - r Zn ytLI e t 7 ie A

3 L

ID 4

3 4

43 41 4 2 5

2F dXiXl Cl U-'

(1

(-

(PIAP/1-OO10250./F9-RO)

REVISION NO.:

PROCEDURE TITLE:

PAGE:

5C GUIDELINES FOR USE OF THE UNIT 1 HIGH 23 of 24 PROCEDURE NO.:

DENSITY SPENT FUEL RACKS 1-0010250 ST. LUCIE UNIT 1 FIGURE 10 FUNNEL HANDLING TOOL ALIGNMENT PLATE (CORRECT POSITION ON FUNNEL)

(.Page 1 of 1 )

Duplex funnel Funnel Handling Tool Alignment Plate (PIAP/I-0010250iF1O-RO)

TOP VIEW

REVISION NO.:

PROCEDURE TITLE:

PAGE:

5C GUIDELINES FOR USE OF THE UNIT 1 HIGH PROCEDURE NO.:

DENSITY SPENT FUEL RACKS 1-0010250 ST. LUCIE UNIT 1 FIGURE 11 FUNNEL FULLY SEATED IN SPENT FUEL STORAGE RACK (Page 1 of 1)

Duplex Funnel Rack

REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM USE CONTROL WIRING DIAGRAMS - UNIT 1 CANDIDATE EXAMINER

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM USE CONTROL WIRING DIAGRAMS UNIT I KA Statement:

KA #:

References:

Ability to obtain and interpret station electrical and mechanical drawings.

2.1.24 (2.8 / 3.1)

Control Wiring Diagram 8770-B-327 Sheet 564 Control Wiring Diagram 8770-B-327 Sheet 501 Control Wiring Diagram 8770-B-327 Sheet 502 Control Wiring Diagram 8770-B-327 Sheet 645 Candidate:

Name Time Start Time Finish Performance Rating:

Sat Unsat Validation Time 15 minutes Examiner:

Signature:

Comments ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 2

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM USE CONTROL WIRING DIAGRAMS UNIT 1 Directions to the candidate for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference normally available in the Control Room to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions I&C would like to inspect the solenoid for Waste Gas Stop Valve V6565 on Unit 1. This will require the solenoid to be de-energized.

Initiating Cue You are the Unit 1 Unit Supervisor. Independently verify the components that need to be operated to de-energize the solenoid for Waste Gas Stop Valve V6565.

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 3

START TIME:

STEP 1:

STANDARD:

COMMENTS:

Determines from one of the following which CWD shows the solenoid of V6565:

Control Wiring Diagram (CWD) Index 8770-B-327 Sheet 1 Lotus Notes on a PC FPL Mainframe on a PC DETERMINES solenoid of V6565 is on 8770-B-327 Sheet 564.

CRITICAL STEP SAT UNSAT Answer Key Attachment 1 i

STEP 2:

STANDARD:

8770-B-327 Sheet 564 Identifies the other CWD that are connected to the solenoid of V6565 is powered from.

DETERMINES solenoid of V6565 is on 8770-B-327 Sheet 564 is connected to the following CWDs:

SH 645: P15B and N15B, 125VDC SH 501: DDD 87 & 88 SH 502: CC 38 & 39 CRITICAL STEP SAT UNSAT COMMENTS:

Answer Key Attachment 1 8770-B-327 Sheet 501 STEP 3:

Determines from where the solenoid of V6565 is powered from:

STANDARD:

DETERMINES Sheet 501 does not provide power to V6565.

SAT COMMENTS:

Answer Key Attachment 2 IUNSAT ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 4

8770-B-327 Sheet 502 STEP 4:

Determines from where the solenoid of V6565 is powered from:

STANDARD:

DETERMINES Sheet 502 does not provide power to V6565.

SAT COMMENTS:

Answer Key Attachment 3 UNSAT 8770-B-327 Sheet 645 CRITICAL STEP 5:

Determines from CWD where on RTGB the solenoid of V6565 is powered STEP from.

STANDARD:

DETERMINES from Sheet 645 to remove fuses in RTGB-105, EE F47 &

SAT F48 125VDC.

_UNSAT COMMENTS:

Answer Key Attachment 4 STEP (done):

Inform Candidate JPM is complete.

STANDARD:

SAT EXAMINER'S CUE:

THIS JPM IS COMPLETE.

COMMENTS:

UNSAT END OF TASK STOP TIME:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 5

CANDIDATE COPY (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Initial Conditions I&C would like to inspect the solenoid for Waste Gas Stop Valve V6565 on Unit 1. This will require the solenoid to be de-energized.

Initiating Cue You are the Unit 1 Unit Supervisor. Independently verify the components that need to be operated to de-energize the solenoid for Waste Gas Stop Valve V6565.

REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM LIQUID RELEASE REQUIREMENTS CANDIDATE EXAMINER

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM LIQUID RELEASE REQUIREMENTS UNIT I KA Statement:

KA #:

References:

Knowledge of the requirements for reviewing and approving release permits.

2.3.6 (2.1 / 3.1) NOP-06.01, Controlled Liquid Release to Circulating Water Discharge Chemistry Pre-Release Calculations C-200, Offsite Dose Calculation Manual Candidate:

Name Time Start Time Finish Performance Rating:

Validation Time Sat Unsat 10 minutes Examiner:

Comments Signature:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 2

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM LIQUID RELEASE REQUIREMENTS UNIT 1 Directions to the candidate for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference normally available in the Control Room to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions Unit 1 is at 100% power. Chemistry has requested a release of the 1 B WMT per LRP Permit # 1-04-55. All equipment is operable with the exception of Liquid Waste Monitor R-6627 which is out of service.

Initiating Cue You are the Unit 1 Unit Supervisor. Process the Liquid Release Permit # 1-04-55 for this release.

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 3

START TIME:

1 -NOP-06.01, Controlled Liquid Release to Circulating Water Discharge STEP 1:

ENSURE Section 3.0, Prerequisites, completed.

STANDARD:

INITIAL Electrical power available and step after reviewing Section 3.0 EVALUATOR NOTE: All equipment is operable per initial conditions COMMENTS:

SAT UNSAT STEP 2:

ENSURE Section 4.0, Prerequisites, completed.

STANDARD:

INITIAL after reviewing Section 4.0 SAT COMMENTS:

UNSAT STEP 3:

REVIEW the Liquid Release Permit for appropriate signatures under AUTHORIZATION.

SAT STANDARD:

VERIFIES signatures and ENTERs 1-04-55 for Permit Number and UNSAT ENTERs 1 B WMT for Tank releasing COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 4

STEP 4:

REVIEW the Equipment Out of Service Log and determine if Channel R-6627, Liquid Waste Monitor has been declared Out of Service.

STANDARD:

DETERMINES R-6627 is Out of Service EVALUATOR NOTE: R-6627 is not operable per initial conditions COMMENTS:

SAT UNSAT If Channel R-6627 is Out of Service, Then PERFORM the following:

STEP 5:

Has Chemistry attached two independent Radioactivity analysis of the tank to the Release Permit?

STANDARD:

CHECK No COMMENTS:

SAT UNSAT If Channel R-6627 is Out of Service, Then PERFORM the following:

STEP 6:

Has Chemistry attached two independent Release Rate Calculations for the tank on the Release Permit?

STANDARD:

CHECK No COMMENTS:

SAT UNSAT ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 5

If Channel R-6627 is Out of Service, Then PERFORM the following:

STEP 7:

Have you arranged for independent verification of the discharge valve alignment?

SAT STANDARD:

COMMENTS:

CHECK No Unit Supervisor is the person who would arrange to this step done UNSAT STEP 8:

If the answer to any of the above questions is "No", Then STOP, do not CRITCAL STEP approve the Liquid Release Permit.

STANDARD:

STOPS, does not approve the Liquid Release Permit.

SAT COMMENTS:

UNSAT STEP (done):

Inform Candidate JPM is complete.

STANDARD:

SAT EXAMINER'S CUE:

THIS JPM IS COMPLETE.

COMMENTS:

UNSAT END OF TASK STOP TIME:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 6

UNIT 1 LIOUID RELEASE PERMIT TANK DATA A. LRP Permit #

B. Date and Time C. Tank Name D. Discharge Volume (Gallons) 1-04-55 21-DEC-2004 03:45 1B WMT 4.0000E+04 lI PRERELEASE DATA (jiCi/ml = micro curies per milliliter)

A. Total Concentration Of Solids 3.574E+06 ttCi/ml B. Total Activity Of Solids 5.411 E+02 zCi C. Tank Recirced As Per COP-01.05 X

Initials D. Minimum Pumps During Release 3

CWP'-

E. Maximum Release Rate During Re],--

),,

"E+02 GPM F. Fraction Of 10 CFR 20 Limits At C "3 v,,

,-02 Fl Canal (Solids) (Admin Limit <0.8)

',(S

.t.j.

G. Total Noble Gas Activity After Dilu

-0 Fg (Gases) (Admin Limit < 1.60E-04) e C

H. Liquid Radwaste Monitor Settings A

L-'*

A Alert Setting 4.500E-03 ACi/ml C

c I Have Verified These Settings Are En z,,, f Monitors Control Module In The Conti Initials I. Liquid Rad Waste Monitor Source Chec 6

Initials J. LRP LIMS Number 234878 Monitor II.

AUTHORIZATION A. Permit Preparer Verifies Release Will.

Signature B. Release Approved By Permit Preparer I Signature C. Release Approved By Chemistry Supr. 1

-= 25000 tzCi N/A Signature D. Release Conditions Approved By ANPS Signature IV.

ACTUAL RELEASE DATA A. Number Of Pumps Running CWP's ICWP's B. Tank Level At Start Of Release C. Date and Time At Start Of Release D. Date and Time At End Of Release E. Tank Level At End Of Release F. Reviewed By ANPS Signature V.

POST RELEASE DATA A. Total Volume This Release Gallons B. Total Activity Of Solids Released

_Ci C. Release Conditions Approved By ANPS Signature

FLORIDA POWER & LIGHT CO.

ST.

LUCIE PLANT CHEMISTRY DEPARTMENT LIQUID RELEASE PERMIT 1 55 FINAL ACTIVITY REPORT FOR PRE-RELEASE CALCULATIONS SAMPLE I.D.

SAMOPLE TIME GEOMETRY FILE:

COUNT TIME SAMPLE VOLUME:

lB WMT 12-21-2004 @ 8:10 3GT67.CLB 1.0000E+03 SEC 1.0000E+03 mls.

FILE: LRP.DAT RELEASE VOLUME:

RELEASE RATE DILUTION PUMPS:

DILUTION RATE SAMPLE #

36 4.0000E+04 gal.

1.7000E+02 GPM 1 ICWP 3

CWP 3.7750E+05 GPM NUCLIDE SYMBOL SB-125 C0-60 H-3 C

FE-55 C

SR-89 C

Y-90 C

Y-90 C

TOTALS SAMPLE UCI/ML

5. 583E-07

1. 783E-06 5.520E-02 9.880E-06 2.400E-08

5. 000E-09

5. 000E-09

2. 342E-06 LRP II.A.

LRP PROGRAM Q.C.

O.K.

E.C.L.

E.C.L.

TANK UCI TANK UCI NUCLIDE UCI/ML FRACTION PRERELEAS POSTRELEA SYMBOL 3.E-05 8.381E-06 8.453E+01 SB-125 3.E-06 2.677E-04 2.700E+02

-60 1.E-03 2.486E-02 1.E-04 4.449E-05 8.E-06 1.351E-06 5.E-07 4.503E-06 7.E-06 3.217E-07 2.519E-02 3.545E+02 F SUB L LRP II.B.

C -

denotes composite -

only used for F SUB L NUCLIDE SYMBOL TOTALS SAMPLE UCI/ML

0. O00E+00 DIL.

CONC TANK UCI TANK UCI NUCLIDE

@ CANAL PRERELEAS POSTRELEA SYMBOL 0.000E+00 0.000E+00 F SUB G

CANDIDATE COPY (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Initial Conditions Unit 1 is at 100% power. Chemistry has requested a release of the 1 B WMT per LRP Permit # 1-04-55. All equipment is operable with the exception of Liquid Waste Monitor R-6627 which is out of service.

Initiating Cue You are the Unit 1 Unit Supervisor. Process the Liquid Release Permit # 1-04-55 for this release.

Procedure No.

ST. LUCIE UNIT 1 1-NOP-06.01 NORMAL OPERATING Current Revision No.

PROCEDURE 7A FPL Effective Date SAFETY RELATED 10/11104

Title:

CONTROLLED LIQUID RELEASE TO THE CIRCULATING WATER DISCHARGE Responsible Department: OPERATIONS REVISION

SUMMARY

Revision 7A - Incorporated PCR 04-2909 to delete step F. of Page 13 of 15 as it is redundant to Step G. (Clyde Price, 10/06/04)

Revision 7 - Incorporated PCR 04-0105 for CR 03-4573, PM03-12-154 to correct switch positions and modify steps 6.3.11 and 6.3.13. (David Albritton, 01/21/04)

AND Incorporated PCR 04-0079 to renumber steps, reword steps, add steps and renumber accordingly. (Winston Ryley, 01/14/04)

Revision 6 - Incorporated TC 03-083 to adjust FIC-6627 to minimum setting and adjust flow.

(Bill Green, 10/30/03)

Revision 5A - Incorporated PCR #03-0353 to add appropriate missing lines. (Clyde Price, 02/14/03)

REVISION 5 - Added note regarding low WMT level and guidance to adjust recirc to maintain flow. (William Green, 08/13/02)

REVISION 4 - Removed 14-day requirement for restoration of rad monitor per change in ODCM (C-200). (Kelly Korth, 05/14/02)

Revision FRG Review Date Approved By Approval Date S 1 OPS 0

09/21/99 R. G. West 09/21/99 DATE Plant General Manager DOCT PROCEDURE Revision FRG Review Date Approved By Approval Date DOCN 1-NOP-06.01 7A N/A SYS Plant General Manager COM COMPLETED J. R. Martin 01/21/04 ITM 7A Designated Approver J. R. Martin 10/06/04 Designated Approver (Minor Correction)

REVISION NO.:

PROCEDURE TITLEK'.

PAGE:

7A CONTROLLED LIQUID RELEASE TO THE 2 of 15 PROCEDURE NO.:

CIRCULATING WATER DISCHARGE 1-NOP-06.01 ST. LUCIE UNIT 1 TABLE OF CONTENTS SECTION PAGE 1.0 PURPO SE.................................................................................................

3

2.0 REFERENCES

3 3.0 PREREQ UISITES......................................................................................

4 4.0 PRECAUTIO NS / LIM ITATIONS...............................................................

4 5.0 RECO RDS REQ UIRED.............................................................................

5 6.0 INSTRUCTIO NS........................................................................................

6 6.1 Initial Conditions.............................................................................

6 6.2 Valve Alignm ent.............................................................................

7 6.3 Starting the Liquid Release..........................................................

10 6.4 Com pleting the Liquid Release...................................................... 14 FIGURES FIG URE 1 LIQ UID RELEASE PERM IT - UNIT 1...........................................

15

REVISION NO.:

PROCEDURE TITLE:

PAGE:

7A CONTROLLED LIQUID RELEASE TO THE 3 of 15 PROCEDURE NO.:

CIRCULATING WATER DISCHARGE 1-NOP-06.01 ST. LUCIE UNIT 1 1.0 PURPOSE 1.1 This procedure provides instructions for the controlled release of liquid from the Waste Monitor Tanks (WMT).

2.0 REFERENCES

NOTE One or more of the following symbols may be used in this procedure:

§ Indicates a Regulatory commitment made by Technical Specifications, Condition of License, Audit, LER, Bulletin, Operating Experience, License Renewal, etc. and shall NOT be revised without Facility Review Group review and Plant General Manager approval.

¶ Indicates a management directive, vendor recommendation, plant practice or other non-regulatory commitment that should NOT be revised without consultation with the plant staff.

T Indicates a step that requires a sign off on an attachment.

2.1 Technical Specifications Appendix B part 2 Technical Requirements Manual 2.2 Updated Final Safety Analysis Report (UFSAR) 0 Section 11.2.2.2 2.3 Management Directives and Regulatory Commitments 0

¶j CR-1045 2.4 Procedures Chemistry Procedure C-200, Offsite Dose Calculation Manual (ODCM)

Radiation Protection Manual COP-01.05, Processing Aerated Liquid Waste 2.5 Miscellaneous Documents P&ID 8770-G-078, Sheets 161, 162, 164, 165

REVISION NO.:

PROCEDURE TITLE:

PAGE:

7A CONTROLLED LIQUID RELEASE TO THE 4 of 15 PROCEDURE NO.:

CIRCULATING WATER DISCHARGE 1-NOP-06.01 ST. LUCIE UNIT 1 3.0 PREREQUISITES INITIAL 3.1 Electrical power is available to the following pumps:

1.

1A Waste Monitor Pump Bkr. 1-40948

2.

1B Waste Monitor Pump Bkr. 1-41756

3.

Liquid Waste Control Panel (LWCP) PP-109, Ckt. 18 4.0 PRECAUTIONS / LIMITATIONS 4.1 Prior to release, the tank contents shall be sampled, analyzed and a Liquid Release Permit (LRP) prepared and approved. Once a sample has been drawn for release purposes, radioactive waste shall NOT be added to the tank.

4.2 The Operator shall perform a release only after receipt of an approved Liquid Release Permit. Form similar to Figure 1.

4.3 The Liquid Waste Monitor shall be in service during a release and frequently observed to assure that the count rate is below the trip point settings as noted on the Release Permit. If the Liquid Waste Monitor is determined to be inoperable, refer to C-200, Offsite Dose Calculation Manual (ODCM), Section 3.3.3.9 for required actions and provisions to proceed with the release.

4.4 If activity reaches the high rate trip setpoint as indicated on the Release Permit, an alarm is activated in the Control Room and Flow Control Valve FCV-6627X trips closed. FCV-6627X may be closed from RTGB-105 to terminate the release at the Operator's discretion. Do not re-initiate a liquid release that has been terminated by a monitor alarm until authorized by the Chemistry Department.

4.5 The minimum number of circulating water (CWP) and/or Intake Cooling Water Pumps (ICWP) should be in service during a release as specified by the Liquid Release Permit. Even though not desirable, a release may be made with only ICW pumps for dilution if administrative limits are not exceeded.

REVISION NO.:

PROCEDURE TITLE:

PAGE:

7A CONTROLLED LIQUID RELEASE TO THE 5

PROCEDURE NO.:

CIRCULATING WATER DISCHARGE 1-NOP-06.01 ST. LUCIE UNIT 1 4.6 The ODCM limits for liquid releases are the following:

1.

The concentration of radioactive material released from the site shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10.4 microcuries / ml total activity.

2.

To ensure that the sum of radioactive releases from multiple release points on site do not exceed the site limits:

A.

No more than one batch release shall be made on site at the same time.

B.

Administrative limits of 80% of the site limits shall be used for a batch release liquid release permit.

C.

Chemistry Department shall ensure as per COP-01.05 that the sum of all continuous and any batch release shall not exceed the site limit.

A continuous release is Steam Generator Blowdown to the discharge canal with primary-to-secondary leakage. A batch release is from a tank identified in the respective reactor unit's operating procedure for controlled liquid release to the circulating water discharge i.e. this procedure.

4.7 Applicable radiation protection, precautions and procedures shall be observed.

5.0 RECORDS REQUIRED 5.1 A completed Liquid Release Permit with the final activity page attachment and this procedure with signed off steps shall be maintained in the plant files in accordance with QI-1 7-PSL-1, Quality Assurance Records.

5.2 Normal Log Entries

REVISION NO.:

PROCEDURE TITLE:

PAGE:

7A CONTROLLED LIQUID RELEASE TO THE 6 of 15 PROCEDURE NO.:

CIRCULATING WATER DISCHARGE 1-NOP-06.01 ST. LUCIE UNIT 1 6.0 INSTRUCTIONS INITIAL 6.1 Initial Conditions

1.

ENSURE Section 3.0, Prerequisites, completed.

2.

REVIEW Section 4.0, Precautions /Limitations.

3.

REVIEW the Liquid Release Permit for appropriate signatures under AUTHORIZATION.

Permit Number Tank releasing CAUTION If the Liquid Waste Monitor is Out of Service, C-200, ODCM Control 3.3.3.9 requires two independent tank sample / analysis and two independent valve alignments to verify the discharge line valving.

4.

¶j REVIEW the Equipment Out of Service Log and determine if Channel R-6627, Liquid Waste Monitor has been declared Out of Service.

5.

If Channel R-6627 is Out of Service, Then PERFORM the following:

YES NO A.

Has Chemistry attached two independent Radioactivity analysis of the tank to the Release Permit?

B.

Has Chemistry attached two independent Release Rate Calculations for the tank on the Release Permit?

C.

Have you arranged for independent verification of the discharge valve alignment?

If the answer to any of the above questions is "No", Then STOP, do not approve the Liquid Release Permit.

END OF SECTION 6.1

REVISION NO.:

PROCEDURE TITLE:

PAGE:

7A CONTROLLED LIQUID RELEASE TO THE 7 of 15 PROCEDURE NO.:

CIRCULATING WATER DISCHARGE 1-NOP-06.01 ST. LUCIE UNIT 1 6.2 Valve Alignment CAUTION If the Liquid Waste Monitor is Out of Service, two independent valve alignments shall be performed to verify the discharge line valving.

I

, a

• I

1.

PERFORM the following valve alignment.

AT CCW PLATFORM VALVE NUMBER DESCRIPTION POSITION INITIAL Waste Monitor Pumps Disch to Disch LOCKED Canal Isol CLOSED V06247 Waste Monitor Tanks Inlet Isol OPEN V06238 Waste Monitor Pumps Discharge Recirc CLOSED Isol V06239 RE-6627 Upstrm Root OPEN V06240 RE-6627 Dwnstrm Root OPEN V06241 FE-6627 Upstrm Root OPEN V06242 FE-6627 Dwnstrm Root OPEN V38175 RE-6627 Demineralized Water Flush CLOSED AT WASTE MONITOR PUMPS VALVE NUMBER DESCRIPTION POSITION INITIAL V06221 1A/1 B Waste Monitor Tank Outlet CLOSED Crossover Isol V06222 1A/1 B Waste Monitor Pump Recirc CLOSED Crossover Isol CLOSED

2.

PERFORM the following valve alignment for the appropriate tank to be discharged: Valve alignment for the non-discharged tank is not necessary.

(Check appropriate tank.)

REVISION NO.:

PROCEDURE TITLE:

PAGE:

7A CONTROLLED LIQUID RELEASE TO THE 8 of 15 PROCEDURE NO.:

CIRCULATING WATER DISCHARGE 1-NOP-06.01 ST. LUCIE UNIT 1 6.2 Valve Alignment (continued)

2.

(continued)

A.

If 1A Waste Monitor Tank is being discharged with the 1A Waste Monitor Pump, Then PERFORM the following alignment:

VALVE NUMBE DESCRIPTION POSITION INITIAL NUMBER V06231 1 B Waste Monitor Pump Disch Isol CLOSED V06207 1A Waste Monitor Tank Outlet Isol OPEN V06208 1A Waste Monitor Pump Suct Isol OPEN V06215 1A Waste Monitor Pump Disch Isol CLOSED V06220 1A Waste Monitor Pump Disch Recirc Isol OPEN Selected to HCV-06-6 Waste Monitor Tanks Inlet 1

to 1 BWMT B.

If 1 B Waste Monitor Tank is being discharged with the 1 B Waste Monitor Pump, Then PERFORM the following alignment:

VALVE NUMBE DESCRIPTION POSITION INITIAL NUMBER V06215 1A Waste Monitor Pump Discharge Isol CLOSED V06223 1 B Waste Monitor Tank Outlet Isol OPEN V06224 1 B Waste Monitor Pump Suct Isol OPEN V06231 1 B Waste Monitor Pump Discharge Isol CLOSED V06235 1 B Waste Monitor Pump Disch Recirc Isol OPEN Selected to HCV-06-6 Waste Monitor Tanks Inlet SAlWMt to 1A WMT

REVISION NO.:

PROCEDURE TITLE:

PAGE:

7A CONTROLLED LIQUID RELEASE TO THE 9 of 15 PROCEDURE NO.:

CIRCULATING WATER DISCHARGE 1-NOP-06.01 ST. LUCIE UNIT 1 6.2 Valve Alignment (continued)

2.

(continued)

C.

If 1A Waste Monitor Tank is being discharged with the 1 B waste monitor pump, Then PERFORM the following alignment:

VALVE NUMBE DESCRIPTION POSITION INITIAL

-NUMBER V06215 1A Waste Monitor Pump Disch Isol CLOSED V06223 1 B Waste Monitor Tank Outlet Isol CLOSED V06224 1 B Waste Monitor Pump Suct Isol OPEN V06231 1 B Waste Monitor Pump Disch Isol CLOSED V06235 1 B Waste Monitor Pump Disch Recirc Isol CLOSED Selected to HCV-06-6 Waste Monitor Tanks Inlet 1

t 1 BWMT V06221 1A/1 B Waste Monitor Tank Outlet OPEN Crossover Isol V06207 1A Waste Monitor Tank Outlet Isol OPEN V06222 1A/1B Waste Monitor Pump Recirc OPEN Crossover Isol V06220 1A Waste Monitor Pump Disch Recirc Isol OPEN D.

If I B Waste Monitor Tank is being discharged with the 1A waste monitor pump, Then PERFORM the following alignment:

VALVE NUMBE DESCRIPTION POSITION INITIAL NUMBER V06231 1 B Waste Monitor Pump Disch Isol CLOSED V06207 1A Waste Monitor Tank Outlet Isol CLOSED V06208 1A Waste Monitor Pump Suct Isol OPEN V06215 1A Waste Monitor Pump Disch Isol CLOSED V06220 1A Waste Monitor Pump Disch Recirc Isol CLOSED HCV-06-6 Waste Monitor Tanks Inlet Selected to 1A WMT V06221 1A/1 B Waste Monitor Tank Outlet OPEN Crossover Isol V06223 1 B Waste Monitor Tank Outlet Isol OPEN V06222 1A/1 B Waste Monitor Pump Recirc OPEN Crossover Isol V06235 1 B Waste Monitor Pump Disch Recirc Isol OPEN END OF SECTION 6.2

REVISION NO.:

PROCEDURE TITLE:

PAGE:

7A CONTROLLED LIQUID RELEASE TO THE PROCEDURE NO.:

CIRCULATING WATER DISCHARGE 1-NOP-06.01 ST. LUCIE UNIT 1 6.3 Starting the Liquid Release NOTE Low WMT level may cause the flow switch for RE-6627 to actuate.

1.

VERIFY that the minimum number of CW or ICW Pumps required by Liquid Release Permit is in service.

2.

ENTER the pumps in operation in section IV of permit.

3.

ENSURE FIC-6627 Manual Control Knob is FULL counterclockwise.

4.

ENSURE FIC-6627 is in MANUAL.

5.

PLACE Liquid Waste Flow Valve Selector to FCV-6627X position.

6.

OPEN FCV-6627X using FIC-6627 Manual Control Knob.

7.

If Waste Monitor Pump 1A is to be used, Then PERFORM the following:

A.

START 1A Waste Monitor Pump

1.

If releasing the 1A Waste Monitor Tank, Then THROTTLE CLOSE V06220, 1A Waste Monitor Pump Discharge Recirc Isol, to attain 20 to 25 psig on PI-06-47A, 1A Waste Monitor Pump Press.

2.

If releasing the 1 B Waste Monitor Tank, Then THROTTLE CLOSED V06235, 1 B Waste Monitor Pump Discharge Recirc Isolation, to attain 20 to 25 psig on PI-06-47A, 1A Waste Monitor Pump Pressure.

B.

OPEN V06215, 1A Waste Monitor Pump Discharge Isol.

C.

If pump discharge pressure does not return to approximately 20 to 25 psig after the discharge valve is opened, Then PERFORM the following:

1.

CLOSE V06215, 1A Waste Monitor Pump Discharge Isolation.

2.

STOP 1A Waste Monitor Pump.

3.

VERIFY correct valve lineup before continuing.

REVISION NO.:

PROCEDURE TITLE:

PAGE:

7A CONTROLLED LIQUID RELEASE TO THE 11 of 15 PROCEDURE NO.:

CIRCULATING WATER DISCHARGE 1-NOP-06.01 ST. LUCIE UNIT 1 6.3 Starting the Liquid Release (continue)

8.

If Waste Monitor Pump 1 B is to be used, Then PERFORM the following:

A.

START 1 B Waste Monitor Pump.

1.

If releasing I B Waste Monitor Tank, Then THROTTLE CLOSED V06235, 1 B Waste Monitor Pump Discharge Recirc Isolation, to attain 20 to 25 psig on PI-06-47B, 1B Waste Monitor Pump Press.

2.

If releasing 1A Waste Monitor Tank, Then THROTTLE CLOSED V06220, 1A Waste Monitor Pump Discharge Recirc Isolation, to attain 20 to 25 psig on PI-06-47B, 1 B Waste Monitor Pump Pressure.

B.

OPEN V06231, 1 B Waste Monitor Pump Discharge Isolation.

C.

If pump discharge pressure does not return to approximately 20 to 25 psig after the discharge valve is opened, Then PERFORM the following:

1.

CLOSE V06231, 1 B Waste Monitor Pump Disch Isol.

2.

STOP 1 B Waste Monitor Pump.

3.

VERIFY correct valve lineup before continuing.

9.

RECORD the following liquid release data in Section IV of LRP:

A.

Start date and time B.

Starting tank level.

10.

LOCK OPEN V21462, Waste Monitor Pumps Disch to Disch Canal Isol

11.

MONITOR FR-6627 and ADJUST FIC-6627 to maintain release flow:

A.

If releasing 1 B Waste Monitor Tank, Then THROTTLE FCV-6627X by adjusting FIC-6627 Manual Control Knob, to attain no greater than 50 gpm on FR-6627.

B.

If releasing 1A Waste Monitor Tank, Then THROTTLE FCV-6627X by adjusting FIC-6627 Manual Control Knob, to attain no greater than 50 gpm on FR-6627.

REVISION NO.:

PROCEDURE TITLE:

PAGE:

7A CONTROLLED LIQUID RELEASE TO THE PROCEDURE NO.:

CIRCULATING WATER DISCHARGE 1-NOP-06.01 ST. LUCIE UNIT 1 6.3 Starting the Liquid Release (continue)

12.

MONITOR liquid radwaste effluent radiation monitor activity (uCi/ml) to ensure rate below those specified on the LRP, for the first few minutes of the release.

13.

MONITOR the Liquid Waste Control Panel for the following:

A.

Local Alarm B.

ENSURE the Waste Monitor pump stops at Lo-Level setpoint.

NOTE If the liquid waste monitor is out of service the release may continue until the Unit Supervisor determines that the release is complete.

C.

When the liquid waste monitor, R-6627, alarms on low sample flow (annunciator X-5), Then PERFORM the following:

1.

If the 1A Waste Monitor Pump is being used for liquid release, Then CLOSE V06215, 1A Waste Monitor Pump Discharge Isolation.

OR If the 1 B Waste Monitor Pump is being used for liquid release, Then CLOSE V06231, 1B Waste Monitor Pump Discharge Isolation.

D.

If the Liquid Release Permit requests a RE-6627 Demin Flush, Then PERFORM the following:

1.

PLACE V06239, RE-6627 Upstrm Root, in the CLOSED position.

2.

NOTIFY the Control Room that Channel RE-6627 is OOS.

3.

PLACE V38175, DMW to RE-6627 Isol, in the OPEN (or throttled OPEN as needed) position.

4.

FLUSH RE-6627 with Demineralized Water for approximately 4 minutes.

5.

PLACE V38175, DMW to RE-6627 Isol, in the CLOSED position.

REVISION NO.:

PROCEDURE TITLE:

PAGE:

7A CONTROLLED LIQUID RELEASE TO THE 13 of 15 PROCEDURE NO-:

CIRCULATING WATER DISCHARGE 1-NOP-06.01 ST. LUCIE UNIT 1 6.3 Starting the

13.

D.

E.

F.

G.

Liquid Release (continue)

INITIAL /IV (continued)

6.

PLACE V06239, RE-6627 Upstrm Root, in the OPEN position.

/

7.

NOTIFY the Control Room that Channel RE-6627 is back in service.

PLACE FCV-6627X Selector switch to the CLOSED position.

PLACE FIC-6627 Manual Control Knob full counter clockwise.

OPEN the Waste Monitor Pump Discharge Isolation:

V06215, 1A Waste Monitor Pump Discharge Isolation OR V06231, 1 B Waste Monitor Pump Discharge Isolation END OF SECTION 6.3

-J

REVISION NO.:

7A PROCEDURE NO.:

1-NOP-06.01 I

IPROCEDURE TITLE:

CONTROLLED LIQUID RELEASE TO THE CIRCULATING WATER DISCHARGE ST. LUCIE UNIT 1 6.4 Completing the Liquid Release

1.

If the Liquid release is complete, Then RECORD the following data in Section IV on Release Permit:

A.

Release stop date and time B.

Monitor Tank ending level

2.

If the Liquid release is complete, Then PERFORM the following valve alignment:

VALVE NUMBER DESCRIPTION POSITION INITIAL V06207 1 A Waste Monitor Tank Outlet Isol OPEN V06208 1A Waste Monitor Pump Suct Isol OPEN V06215 1A Waste Monitor Pump Disch Isol CLOSED V06220 1A Waste Monitor Pump Disch Recirc Isol OPEN V21462 V06221 Waste Monitor Pumps Disch to Disch Canal Isol 1A/1 B Waste Monitor Tank Outlet Crossover Isol LOCKED CLOSED

--- 4 CLOSED V06222 1A/1B Waste Monitor Pump Recirc CLOSED 0C rossover Isol C O E V06223 1 B Waste Monitor Tank Outlet Isol OPEN V06224 1 B Waste Monitor Pump Suct Isol OPEN V06231 1B Waste Monitor Pump Disch Isol CLOSED V06235 1 B Waste Monitor Pump Disch Recirc Isol{

OPEN

3.

ROUTE completed release package to Nuclear Plant Supervisor / Assistant Nuclear Plant Supervisor for review.

END OF SECTION 6.4

REVISION NO.:

PROCEDURE TITLE:

PAGE:

7A CONTROLLED LIQUID RELEASE TO THE 15 of 15 PROCEDURE NO.:

CIRCULATING WATER DISCHARGE 1-NOP-06.01 ST. LUCIE UNIT 1 FIGURE 1 LIQUID RELEASE PERMIT - UNIT 1 (Page 1 of 1)

I. TANK DATA A. IRP Permit #

B. Date and Time C. Tank Name D. Discharge Volume (Gallons)

II. PRE-RELEASE DATA (pCi/ml = micro curies per milliliter)

A.

Total Concentration Of Solids pCi/ml B.

Total Activity Of Solids IpCi C.

Tank Recirced As Per COP-01.05 Initials D.

Minimum Pumps During Release CWPs ICWPs E.

Maximum Release Rate During Release GPM F.

Fraction Of 10 CFR 20 Limits At Canal FI Canal (Solids) (Admin Limit < 0.8)

G.

Total Noble Gas Activity After Dilution Fg (Gases) (Admin Limit < 1.60E-04)

H.

Liquid Radwaste Monitor Settings Alert Setting pCi/ml High Setting pCi/ml I Have Verified These Settings Are Entered On The Monitors Control Module In The Control Room.

Initials I.

Liquid Rad Waste Monitor Source Check Performed By:

Initials J.

LRP LIMS Number Monitor Source Check LIMS Number Ill. AUTHORIZATION A.

Permit Preparer Verifies Release Will Not Exceed Admin Limits Signature B.

Release Approved By Permit Preparer If II.B Is. 25000 pCi Signature C.

Release Approved By Chemistry Supv If 11.1 Is > 25000 pCi Signature D.

Release Conditions Approved by ANPS:

Signature IV. ACTUAL RELEASE DATA A.

Number Of Pumps Running CWPs ICWPs B.

Tank Level At Start Of Release C.

Date And Time At Start Of Release D.

Date And Time At End Of Release E.

Tank Level At End Of Release F.

Reviewed By ANPS Signature V.

POST RELEASE DATA A.

Total Volume This Release Gallons B.

Total Activity Of Solids Released pCi C.

Post Release Reviewed By Chemistry Supervisor Signature SOPS DATE DOCT DOCN_

SYS COMP ITM_

Page 18 of 230 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 25 OFFSITE DOSE CALCULATION MANUAL (ODCM)

INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION CONTROLS 3.3.3.9 In accordance with St. Lucie Plant TS 6.8.4.f.1), the radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their Alarm/Trip Setpoints set to ensure that the limits of Control 3.11.1.1 are not exceeded. The Alarm/Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY:

At all times.

ACTION:

a.

With a radioactive liquid effluent monitoring instrumentation channel Alarm/Trip Setpoint less conservative than required by the above control, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable or change the setpoint so it is acceptably conservative.

b.

With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12.

Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why this inoperability was not corrected in a timely manner.

c.

Report all deviations in the Annual Radioactive Effluent Release Report.

SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST at the frequencies shown in Table 4.3-8.

St. Lucie Plant ODCM Controls

Page 19 of 230 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 25 OFFSITE DOSE CALCULATION MANUAL (ODCM)

TABLE 3.3-12 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION

1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release a)

Liquid Radwaste Effluent Line 1

35 b)

Steam Generator Blowdown 1/SG 36, 37 Effluent Line

2. Flow Rate Measurement Devices a)

Liquid Radwaste Effluent Line N.A.

38 b)

Discharge Canal N.A.

38 c)

Steam Generator Blowdown N.A.

38 Effluent Lines SG - Denotes Steam Generator St. Lucie Plant ODCM Controls

Page 20 of 230 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 25 OFFSITE DOSE CALCULATION MANUAL (ODCM)

TABLE 3.3-12 (Continued)

ACTION STATEMENTS ACTION 35 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a release:

/R25

a.

At least two independent samples are analyzed in accordance with the Surveillance Requirement for concentration limit of Control 4.11.1.1.1. and

b.

At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 36 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 2.E-07 micro-Curie/ml:

a.

At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />(1) when the specific activity of the secondary coolant is greater than 0.01 micro-Curies/gram DOSE EQUIVALENT 1-131 or

b.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />(') when the specific activity of the secondary coolant is less than or equal to 0.01 micro-Curies/gram DOSE EQUIVALENT 1-131.

St. Lucie Plant ODCM Controls

REGION II ST. LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM LOSS OF CONTROL ROOM ANNUNICATORS UNIT 1 CANDIDATE EXAMINER

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM LOSS OF CONTROL ROOM ANNUNICATORS UNIT 1 KA Statement:

Knowledge of operator response to loss of all annunciators.

KA#:

2.4.32 (3.3 / 3.5)

References:

ONP 2-100.03, Partial or Complete Loss of Annunicators EPIP-01, Classification of Emergencies EPIP-08, Off-Site Notifications and Protective Action Recommendations Candidate:

Name Time Start Time Finish Performance Rating:

Validation Time Sat Unsat 30 minutes (Time Critical)

Examiner:

Signature:

Comments ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 2

REGION II ST LUCIE NUCLEAR PLANT INITIAL LICENSE EXAMINATION ADMINISTRATIVE JPM LOSS OF CONTROL ROOM ANNUNICATORS UNIT 1 Directions to the candidate for Administrative JPMS:

I will explain the initial conditions and state the task to be performed. You will be allowed to use any reference normally available in the Control Room to complete the task. Ensure you indicate to me when you finish your assigned task by returning the material needed for the task that I provided to you.

Initial Conditions Unit 1 is at 90% power performing a downpower to 45% due to electrical bus problems.

The Reactor Operator has just reported that numerous annunicators are not working.

Initiating Cue You are the Shift Manager. Unit 1 has just tested all annunicators and determined that the annunicators A, B, C, D, K, L, M, N, P, Q, R & S are not functioning. 10 Meter wind speed is 12 mph and direction is 90. Complete the appropriate procedures as necessary. This is a time-critical JPM.

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 3

START TIME:

ONP 2-100.03, Partial or Complete Loss of Annunicators":

STEP 1:

RECORD the time that annunciators were lost.

SAT STANDARD:

RECORD current time.

UNSAT COMMENTS:

STEP 2:

TEST all Control Room alarm panels to determine the extent of any malfunction.

SAT STANDARD:

DETERMINE annunicators A, B, C, D, K, L, M, N, P, Q, R & S are not functioning.

UNSAT COMMENTS:

STEP 3:

DETERMINE the affected annunciator panels (A, B, C, LR, etc.).

SAT STANDARD:

DETERMINE annunicators A, B, C, D, K, L, M, N, P, Q, R & S are not functioning..

_UNSAT COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 4

STEP 4:

From the table below, DETERMINE the percentage of Safety System Annunciators that are lost by adding the percent of total for each affected panel.

CRITICAL STEP STANDARD:

DETERMINE the percentage > 75%

SAT A

8.6%

B 8.6%

C 0.8%

D 0.0%

K 4.8%

L 6.3%

M 6.3%

N 4.2%

P 6.7%

Q 10.3%

R 10.9%

S 10.3%

TOTAL 77.9%

UNSAT COMMENTS:

CRTIA STEP 5:

STANDARD:

If the percentage of safety system annunciators exceeds 50%, Then EVALUATE and IMPLEMENT the E-Plan as required in EPIP-01, Classification of Emergencies.

IMPLEMENT EPIP-01, Classification of Emergencies 8.B. LOSS OF ALARMS / COMMUNICATION /MONITORING CRITICAL STEP SAT UNSAT COMMENTS:

J ____________________

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 5

EPIP-01 Attachment 1 Step 8.B Loss of Alarms/Communication/Monitoring CRITICAL STEP STEP 6:

Classifies EAL ALERT per EPIP-01 STANDARD:

CLASSIFIES ALERT due to Unplanned loss of most (greater than 75%) or all safety system annunicators and Plant transient in progress.

SAT UNSAT EXAMINER'S NOTE:

Record the time initial event Declaration is made This must be within 15 of JPM Start Time Your task is to now complete a FLORIDA NUCLEAR PLANT NOTIFICATION FORM using EPIP-08.

HAND STUDENT EPIP-08 EXAMINER'S CUE:

EXAMINER'S NOTE:

COMMENTS:

EPIP-08 Attachment 1 Step 1A STEP 7:

Check appropriate box for drill or actual emergency as the case may be.

During exercises, drills, or tests, each message shall be checked THIS IS A DRILL.

CRITICAL STEP SAT UNSAT STANDARD:

CHECK THIS IS A DRILL COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 6

I EPIP-08 Attachment 1 Step 2A Enter today's date.

STEP 8:

CRITICAL STEP SAT UNSAT STANDARD:

ENTER the current date.

EVALUATOR'S NOTE: 2B is completed when contact with State Warning Point is made COMMENTS:

EPIP-08 Attachment 1 Step 2C Enter the name of the person making the notification call.

I STEP 9:

CRITICAL STEP SAT UNSAT STANDARD:

ENTER Candidates name.

COMMENTS:

EPIP-08 Attachment 1 Step 2D Enter the message number.

STEP 10:

CRITICAL STEP SAT UNSAT STANDARD:

ENTER 1 COMMENTS:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 7

EPIP-08 Attachment 1 Step 2E Check where notification is being made from.

STEP 11:

STANDARD:

CHECK Control Room COMMENTS:

CRITICAL STEP SAT UNSAT STEP 12:

EPIP-08 Attachment 1 Step 3B Check the box for the facility from which the notification is being made.

CRITICAL STEP SAT UNSAT STANDARD:

CHECK St. Lucie Unit 1 COMMENTS:

I1 EPIP-08 Attachment 1 Step 4A Check the box corresponding to current accident classification declared.

STEP 13:

CRITICAL STEP SAT UNSAT STANDARD:

CHECK Alert COMMENTS:

L _____________________

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 8

EPIP-08 Attachment 1 Step 5A STEP 14:

Check the box for the appropriate plant site for the emergency declaration.

CRITICAL STEP SAT UNSAT STANDARD:

CHECK Emergency Declaration.

COMMENTS:

ti-R-uJ Attachment 1 Sitep 5 STEP 15:

Enter the date and time when the current emergency classification was declared CRITICAL STEP SAT UNSAT STANDARD:

ENTER Date and Time EXAMINER'S NOTE: Should be same time as Step 1 of JPM COMMENTS:

I__

EIPhI-U8 Attachment 1 Step 6B STEP 16:

Reason for Emergency Declaration STANDARD:

CHECK "B" Description ENTER Unplanned loss of most (greater than 75%) or all safety system annunicators and plant transient in progress.

CRITICAL STEP SAT UNSAT COMMENTS:

I I

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 9

EPIP-08 Attachment 1 Step 7A Additional Information or Update STEP 17:

STANDARD:

CHECK "A" None COMMENTS:

SAT UNSAT EPIP-08 Attachment 1 Step 8 Weather Data.

STEP 18:

CRITICAL STEP SAT UNSAT STANDARD:

A. Wind direction 900 B. Downwind Sectors Affected M, N, P COMMENTS:

EPIP-08 Attachment 1 Step 9A Release Status STEP 19:

CRITICAL STEP SAT UNSAT STANDARD:

CHECK "A" None (Go To Item 11)

COMMENTS:

I.________________________

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 10

STEP 20:

STANDARD:

EPIP-08 Attachment 1 Step 10 Release Significance Category Do Not Check Any Box in Item 10 SAT UNSAT COMMENTS:

STEP 21:

STANDARD:

EPIP-08 Attachment 1 Step 1 1A Determination of Protective Actions Recommendations (PARs)

CHECK "A" No recommended Actions at this time i

CRITICAL STEP SAT UNSAT COMMENTS:

STEP 22:

STANDARD:

EPIP-08 Attachment 1 Step 11 B Utility Recommended Protective Actions Leave "B" blank CRITICAL STEP SAT UNSAT COMMENTS:

I _______________________

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 11

EPIP-08 Attachment 1 Step 11 C Consideration Issuance of KI:

STEP 23:

CRITICAL STEP SAT STANDARD:

CHECK NO UNSAT COMMENTS:

Requires G.E. and Release in Progress to check YES I. ___________________________

EIP'IP-08 Attachment 1 Step 12 STEP 24:

Plant Conditions STANDARD:

Leave Blank COMMENTS:

SAT

_UNSAT STEP 25:

EC or RM Approval CRITICAL STEP STANDARD:

Sign, Date and Time on EC Approval Signature SAT UNSAT EXAMINER'S NOTE:

RECORD THE TIME TASK IS COMPLETE, COLLECT THE STATE NOTIFICATION FORM.

• MUST BE < 15 MINUTES FROM STEP 6 CLASSIFICATION TIME.

COMMENTS:

END OF TASK I ________________________________

STOP TIME:

ST. LUCIE TRAINING DEPT.

ADMINISTRATIVE JPM PAGE 12

A T T A C H M E N T 1 I

FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM (Page 1 of 1)

On-line Verification:

El SWP/DEM El St. Lucie County

[-

Martin County

1.

A. ID THIS IS A DRILL

2.

A.

Date: D/AT/E D.

Message Number:

1

3.

Site:

A. E] Crystal River Unit 3 D. El Turkey Point Unit 3

4.

Emergency Classification:

A B

5.

A. 0 Emergency Declaration:

B. El THIS IS AN EMERGENCY B. Contact Time:

C. Reported by: (Name) Candidate E. Reported from: 0 Control Room El TSC El EOF B. Z St. Lucie Unit 1 E. El Turkey Point Unit 4 C. El St. Lucie Unit 2 C. El Site Area Emergency D. El General Emergency E Notification of Unusual Event 0 Alert B.

El Emergency Termination:

Date: D/AT/E Time:

TIME

6.

Reason for Emergency Declaration:*

A.

El EAL Number OR B. 0

==

Description:==

Unplanned loss of most (greater than 75%) or all safety system annunicators and Plant transient 7.

-in proaress.

Additional Informnation or Update:

A.

0l None OR B. El

8.

Weather Data:

A. Wind direction from 90 degrees

9.

Release Status:

A. 0 None (Go to Item 11)

10.

Release Significance Category (at the Site Boundary):

B. Downwind Sectors Affected:

M

_N.,

NP B. El Is occurring C. El Has occurred, but stopped A.

B.

C.

D.

El Information not available at this time.

El Release within normal operating limits (< 3.5 E-1 Ci/sec noble gas, _* 4.6 E-5 Ci/sec iodine)

E]

Non-Significant Fraction of PAG Range (release is > normal limits and < 500 mrem TEDE and 1000 mrem CDE)

El PAG Range (_> 500 mrem TEDE or _ 1000 mrem CDE)

11.

Utility Recommended Protective Actions:

A.

0D No recommended actions at this time.

B.

El The utility recommends the following protective actions:

El Miles No Action Sectors Evacuate Sectors Shelter Sectors 0-2 2-5 5-10 OR Shelter Zones / Areas:

Evacuate Zones / Areas:

C.

Consider Issuance of KI:

El Yes 0 No If form is completed in the Control Room, go to Item 15. If completed in the TSC or EOF, continue with item 12.

12.

Plant Conditions:

13.

Weather Data:

A. Reactor Shutdown? [] Yes E] No C. Containment Intact? El Yes El No B. Core Adequately Cooled?

E] Yes E] No D. Core Condition: [] Stable

[E Degrading A. Wind Speed __

mph B. Stability Class __

14.

Additional Release Information:

El N/A OR A. El Noble Gases Curies per second B. El lodines Curies per second C. Airborne:

Date Started

/

/

Time Started Date Stopped

/

/

D. Liquid:

Date Started

/

/

Time Started Date Stopped

/

/

Time Stopped __

Time Stopped __

Distance 1 Mile (Site Boundary) 2 Miles 5 Miles 10 Miles Projected Thyroid Dose (CDE) for 1 Hour E.

mrem G.

mrem I.

mrem K.

mrem Prniontprd Tntni fnn-q (TEDEF) for 1 Hnujr F.

mrem H.

mrem J.

mrem L.

mrem VVOI oiyr OLUIC.

~.bO, J*I.JOLC Date: D / AT / E Date:

/

/

Time:

Time Time: __

15.

Message Received By: Name:

If emergency class escalation is known to be necessary and a new notification form will be transmitted within 15 minutes, then you may go to line 15.

1 '

ý t\\, 'E (2 -

V E--

PSL-F070 EPIP-08, Off-Site Notifications and Protective Action Recommendations Effec' Form tive Date: 08/29/03

CANDIDATE COPY (TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF ANSWER)

Initial Conditions Unit 1 is at 90% power performing a downpower to 45% due to electrical bus problems.

The Reactor Operator has just reported that numerous annunicators are not working.

Initiating Cue You are the Shift Manager. Unit 1 has just tested all annunicators and determined that the annunicators A, B, C, D, K, L, M, N, P, Q, R & S are not functioning. 10 Meter wind speed is 12 mph and direction is 90. Complete the appropriate procedures as necessary. This is a time-critical JPM.

REVISION NO.:

PROCEDURE TITLE:

PAGE:

1B PARTIAL OR COMPLETE LOSS 2 of 6 PROCEDURE NO.:

OF ANNUNCIATORS 1-ONP-100.03 ST. LUCIE UNIT 1 TABLE OF CONTENTS SECTION PAGE 1.0 P U R P O S E................................................................................................

.. 3

2.0 REFERENCES

3 3.0 RECORDS REQUIRED.............................................................................

3 4.0 ENTRY CONDITIONS...............................................................................

3 5.0 EXIT CONDITIONS...................................................................................

3 6.0 OPERATOR ACTIONS................................................................................

4 APPENDICES APPENDIX A SAFETY SYSTEM ANNUNCIATORS................................... 5 APPENDIX B POW ER SUPPLIES.............................................................. 6

REVISION NO.:

PROCEDURE TITLE:

PAGE:

1B PARTIAL OR COMPLETE LOSS 3 of 6 PROCEDURE NO.:

OF ANNUNCIATORS 1-ONP-100.03 ST. LUCIE UNIT 1 1.0 PURPOSE 1.1 This procedure provides guidance for resolving conditions resulting from the loss of Control Room annunciators. The actions listed are intended to be a guide in responding to the loss of annunciators and are NOT intended to be a substitute for good judgement based on plant conditions.

2.0 REFERENCES

NOTE One or more of the following symbols may be used in this procedure:

§ Indicates a Regulatory commitment made by Technical Specifications, Condition of License, Audit, LER, Bulletin, Operating Experience, License Renewal, etc. and shall NOT be revised without Facility Review Group review and Plant General Manager approval.

¶ Indicates a management directive, vendor recommendation, plant practice or other non-regulatory commitment that should NOT be revised without consultation with the plant staff.

T Indicates a step that requires a sign off on an attachment.

2.1 UFSAR Section 7.5.1.6.3 2.2

§1 EPIP-01, Classification of Emergencies.

2.3 CWD 8770-B-327.

2.4 Annunciator Response Procedures 3.0 RECORDS REQUIRED 3.1 RCO Chronological log.

4.0 ENTRY CONDITIONS 4.1 Plant parameters exceed alarm setpoints without annunciation.

4.2 Annunciator check indicates a complete or partial loss of annunciation.

5.0 EXIT CONDITIONS 5.1 All annunciators have been returned to operation and are functioning properly.

REVISION NO.:

PROCEDURE TITLE:

PAGE:

1B PARTIAL OR COMPLETE LOSS 4 of 6 PROCEDURE NO.:

OF ANNUNCIATORS 1-ONP-100.03 ST. LUCIE UNIT 1 6.0 OPERATOR ACTIONS INSTRUCTIONS CONTINGENCY ACTIONS

1. RECORD the time that annunciators were lost.

2. TEST all Control Room alarm panels to determine the extent of any malfunction.

3.

§1 IMPLEMENT Appendix A.

4.

PERFORM the following:

• INCREASE the frequency of monitoring RTGB and local indications for plant equipment affected.

" Periodically EXAMINE available reflash panels on the affected annunciator panels.

5.

CHECK the annunciator power supplies in accordance with Appendix B.

6.

CONTACT I&C for trouble-shooting and repair.

END OF SECTION 6.0

REVISION NO.:

PROCEDURE TITLE:

PAGE:

1B PARTIAL OR COMPLETE LOSS 5 of 6 PROCEDURE NO.:

OF ANNUNCIATORS 1-ONP-100.03 ST. LUCIE UNIT 1 APPENDIX A SAFETY SYSTEM ANNUNCIATORS (Page 1 of 1)

NOTE The total below assumes a complete loss of an annunciator panel(s) resulting in the loss of all the safety system annunciators associated with that panel.

1. DETERMINE the affected annunciator panels (A, B, C, LR, etc.).

2. From the table below, DETERMINE the percentage of Safety System Annunciators that are lost by adding the percent of total for each affected panel.

3. If the percentage of safety system annunciators exceeds 50%, Then EVALUATE and IMPLEMENT the E-Plan as required in EPIP-01, Classification of Emergencies.

PERCENTAGE OF SAFETY SYSTEM ANNUNICATORS PER PANEL PANEL

% OF TOTAL A

8.6%

B 8.6%

C 0.8%

D 0.0%

E 2.3%

F 2.7%

G 3.4%

H 5.5%

J 1.3%

K 4.8%

L 6.3%

PANEL

% OF TOTAL M

6.3%

N 4.2%

P 6.7%

Q 10.3%

R 10.9%

S 10.3%

LR 0.8%

X 2.3%

Y 3.1%

z 0.8%

END OF APPENDIX A

REVISION NO.:

PROCEDURE TITLE:

PAGE:

1BI PARTIAL OR COMPLETE LOSS 6 of 6 PROCEDURE NO.:

OF ANNUNCIATORS 1-ONP-100.03 ST. LUCIE UNIT 1 APPENDIX B POWER SUPPLIES (Page 1 of 1)

NOTE The neon light on the back of RTGB alarm panels indicates the DC converter is operating. After power is removed from the panel, it may be necessa to remove and replace the fuse to restart the converter.

1. VERIFY the following power supplies to the affected Control Room annunciators and reset as required.

RTGB ANN. PAN.

POWER SUPPLY GROUND DET.

101 A, B, C, D RTGB 101 KKK F-4, F-12 lAB DC CKT 6 GD-1 102 E,F,G RTGB 101 KKK F-3, F-11 lAB DC CKT6 GD-2 103 H, J RTGB 101 KKK F-5, F-13 lAB DC CKT 3 GD-3 104 K, L RTGB 101 KKK F-6, F-14 lAB DC CKT 3 GD-4 105 M, N RTGB 101 KKK F-8, F-16 lAB DC CKT 3 GD-5 106 P, Q, R, S RTGB 101 KKK F-7, F-15 lAB DC CKT 3 GD-6 NOTE Power supply RTGB 101 KKK F-7, F-15 lAB DC Ckt. 3 also supplies seismic monitoring.

CRAC Panel Y CRAC Panel Z Rad. Monitor Fuses 11F5, 11F7 Fuses 11F10, 11F12 F-10 in Rad. Mon. Cabinet 1 B DC CKT 25 1B DC CKT 25 DC PP 119 CKT 1

2. TEST all the Control Room annunciator panels from the Control Room test panels.

3. TEST all the reflash modules feeding annunciators on the affected panels.

NOTE I&C Department assistance may be required.

4. SELECT an annunciator on each affected panel and functionally CHECK by generating the annunciator from the field.

5. CONTACT I&C Department to investigate and troubleshoot the problem.

END OF APPENDIX B

Procedure No.

ST. LUCIE PLANT EPIP-01 EMERGENCY PLAN Current Revision No.

IMPLEMENTING PROCEDURE 8

FPL Effective Date SAFETY RELATED 10/29/04

Title:

CLASSIFICATION OF EMERGENCIES Responsible Department: EMERGENCY PLANNING REVISION

SUMMARY

Revision 8 - Incorporated PCR 04-3018 to revise classification table to incorporate changes resulting from the New Safeguards Contingency Plan. (J. R. Walker, 10/27/04)

Revision 7 - Incorporated PCR #04-2011 to incorporate instructions from NRC Safe Guards Advisory for Operating Power Reactors, SA-04-07. (J. R. Walker, 06/28/04)

Revision 6 - Incorporated PCR #03-0403 to delete wording regarding technical specification limits and correctly place symbols. (J. R. Walker, 02/21/03)

Revision 5 - Clarified EALs under alert. (J. R. Walker, 07/25/02)

Revision 4 - Revised lAW revision to E-Plan (R40). Revised initiating condition for RCS leakage. Added EALs under security threat initiating condition. Added definitions for EAL and IC. Added guidance for multiple and dual unit events. Made editorial and administrative changes. (J.R. Walker, 05/23/02)

Revision 3 - Added PMAI references, added definitions for OCA, PA and power block, clarified classification guidance and made editorial/administrative changes.

(J. R. Walker, 02/09/01)

Revision 2 - Clarified initiating conditions and emergency action levels to correspond to changes in the PSL emergency plan in accordance with PMAI PM99-09-154, defined classification table and made editorial changes. (J. R. Walker, 10/13/00)

Revision FRG Review Date Approved By Approval Date S

OPS 0

12/15/97 J. Scarola 12/15/97 DATE Plant General Manager DOCT PROCEDURE Revision FRG Review Date Approved By Approval Date DOCN EPIP-01 8

10/27/04 G. L. Johnston 10/27/04 SYS Plant General Manager COM COMPLETED N/A ITM 8

Designated Approver N/A Designated Approver (Minor Correction)

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EPIP-01 ST. LUCIE PLANT TABLE OF CONTENTS SECTION PAGE 1.0 P U R P O S E.................................................................................................

.. 3

2.0 REFERENCES

/ RECORDS REQUIRED / COMMITMENT DOCUMENTS.. 3 3.0 R ES PO N S IB ILIT IE S.................................................................................

4 4.0 D E F IN IT IO N S..........................................................................................

.. 5 5.0 IN S T R U C T IO N S.......................................................................................

9 ATTACHMENTS ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE............................. 13

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EPIP-01 ST. LUCIE PLANT 1.0 PURPOSE This procedure provides instructions on the classification of emergencies at St.

Lucie Plant.

Emergency classifications in order of increasing seriousness are:

Unusual Event Alert Site Area Emergency General Emergency Specific criteria are provided to assure proper escalation and de-escalation between emergency classification levels.

2.0 REFERENCES

/ RECORDS REQUIRED / COMMITMENT DOCUMENTS NOTE One or more of the following symbols may be used in this procedure:

§ Indicates a Regulatory commitment made by Technical Specifications, Condition of License, Audit, LER, Bulletin, Operating Experience, License Renewal, etc. and shall NOT be revised without Facility Review Group review and Plant General Manager approval.

¶1 Indicates a management directive, vendor recommendation, plant practice or other non-regulatory commitment that should NOT be revised without consultation with the plant staff.

T Indicates a step that requires a sign off on an attachment.

2.1 References

1.

St. Lucie Plant Radiological Emergency Plan (E-Plan)

2.

E-Plan Implementing Procedures (EPIP 00-13)

3.

C-200, Offsite Dose Calculation Manual (ODCM)

4.

AP 0010502, Oil and Hazardous Material Emergency Response Plan

5.

$1 NUREG-1022, Section 3.1.1

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EPIP-01 ST. LUCIE PLANT 2.1 References (continued)

6.

¶12 NRC IEN No. 85-80, Timely Declaration of an Emergency Class, Implementation of an Emergency Plan, and Emergency Notifications, October 15, 1985

7.

¶3 NRC EPPOS No. 2, Emergency Preparedness Position (EPPOS) on Timeliness of Classification of Emergency Conditions, August, 1995

8.

¶4 PMAI PM98-01-017, Loss of Seismic Monitoring Capability 2.2 Records Required The basis for classifying an emergency condition shall be recorded in appropriate emergency logs.

2.3 Commitment Documents

§1 CR 00-0614 (RCS leakage during shutdown cooling)

§2 PMAI PM99-09-154 (IC and EAL changes submitted under FPL letter L-98-2000)

T ¶5 NRC Safeguards Advisory for Operating Power Reactors, SA-04-07 3.0 RESPONSIBILITIES 3.1 Shift Manager (SM)

1.

The Shift Manager is responsible to promptly classify abnormal situations into one of the four defined categories.

2.

If an emergency has been declared, the Shift Manager is responsible for assuming the position of Emergency Coordinator and retaining this position until relieved.

3.2 Emergency Coordinator (EC)

The Emergency Coordinator is responsible to continually evaluate changes in plant conditions against the classification table in this procedure.

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5 EPIP-01 ST. LUCIE PLANT 4.0 DEFINITIONS 4.1 Emergency Action Level (EAL)

1.

A pre-determined, site-specific, observable threshold for a plant Initiating Condition that places the plant in a given emergency class. An EAL can be:

an instrument reading; an equipment status indicator; a measurable parameter (on-site or off-site); a discrete, observable event; results of analyses; entry into specific emergency operating procedures; or another phenomenon which, if it occurs, indicates entry into a particular emergency class.

4.2 Emergency Classes

1.

Unusual Event This classification is represented by off-normal events or conditions at the plant for which no significant degradation of the level of safety of the plant has occurred or is expected. Any releases of radioactive material which may have occurred or which may be expected are minor and constitute no appreciable health hazard.

2.

Alert This classification is represented by events which involve an actual or potential substantial degradation of the level of safety of the plant combined with a potential for limited uncontrolled releases of radioactivity from the plant.

3.

Site Area Emergency This classification is composed of events which involve actual or likely major failures of plant functions needed for protection of the public combined with a potential for significant uncontrolled releases of radioactivity from the plant.

4.

General Emergency This classification is composed of events which involve actual or imminent substantial core degradation and potential loss of containment integrity combined with a likelihood of significant uncontrolled releases of radioactivity from the plant.

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EPIP-01 ST. LUCIE PLANT 4.3 Classification Table A composite of Initiating Conditions (ICs) and their Emergency Action Levels (EALs) used to evaluate off normal/emergency conditions resulting in declaration of one of the four Emergency Classes, as appropriate. The Table is arranged in the following categories:

1.

Events Affecting Primary Pressure A.

Abnormal Primary Leak Rate B.

Abnormal Primary/Secondary Leak Rate C.

Loss of Secondary Coolant

2.

Abnormal Radiation, Contamination and Effluent Releases A.

Uncontrolled Effluent Release B.

High Radiation Levels in Plant

3.

Fires, Explosions

4.

Accident Involving Fuel A.

Fuel Element Failure B.

Fuel Handling

5.

Natural Emergencies A.

Earthquake B.

Hurricane C.

Tornado D.

Abnormal Water Level

6.

Miscellaneous Events A.

Increased Awareness or Potential Core Melt

7.

Electrical Malfunctions A.

Loss of Power

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EPIP-01 ST. LUCIE PLANT 4.3 Classification Table (continued)

8.

Degradation of Control Capabilities A.

Loss of Plant Control Functions B.

Loss of Alarms, Communications, Monitoring

9.

Hazards to Station Operation A.

Aircraft, Missile B.

Turbine Failure C.

Toxic or Flammable Gas

10.

Security Threat 4.4 Initiating Condition (IC)

1.

One of a predetermined subset of nuclear power plant conditions where either the potential exists for a radiological emergency, or such an emergency has occurred.

4.5 Plant - The St. Lucie Plant, Unit 1 and Unit 2 4.6 Site - A general term referring to the location of the St. Lucie Nuclear Power Plant.

Other terms related to the site are given below:

1.

Owner Controlled Area - That portion of FPL property surrounding and including the St. Lucie Nuclear Power Plant which is subject to limited access and control as deemed appropriate by FPL.

2.

Protected Area - The area (within the Owner Controlled Area) occupied by the nuclear units and associated equipment and facilities enclosed with the security perimeter fence. The area within which accountability of personnel is maintained in an emergency.

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8 of 32 EPIP-01 ST. LUCIE PLANT 4.6 Site (continued)

3.

§2 Power Block - Structures, systems or components in the areas listed below that support the production of power. This includes any equipment needed for the direct generation of power or necessary for safe operation and/or shutdown of one or both of the reactors.

A.

Reactor Containment and Shield Buildings B.

Reactor Auxiliary Buildings including the following areas:

1.

Refueling Water Tank (RWT)

2.

Component Cooling Water (CCW) platform area

3.

Diesel Generator Buildings and Fuel Oil Storage Tanks

4.

Fuel Handling Building

5.

Primary Water Tank and Pumps C.

Intake Area D.

Discharge Canal & Headwall E.

Ultimate Heat Sink Structure F.

Fire Protection System including the fire pumps and the City Water Storage Tanks (CWST), but not including parts of the system associated with the North or South Service Buildings or other outlying facilities.

G.

Turbine Buildings (all levels)

H.

Condensate Storage Tanks (CST)

I.

Main, Auxiliary and Startup Transformers J.

Steam Trestles K.

Turbine Lube Oil Storage Tanks L.

Gas House

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9 EPIP-01 ST. LUCIE PLANT 5.0 INSTRUCTIONS 5.1 Direct Initial Investigative and Mitigating Actions to Address the Event

1.

If the event involves entry into the Off-Normal Operating Procedures (ONOPs) or Emergency Operating Procedures (EOPs), Then perform steps per ONOPs or EOPs until appropriate or directed to classify event.

2.

If the event involves a release of hazardous materials to the environment, Then respond per AP 0010502, Oil and Hazardous Material Emergency Response Plan.

3.

If the event involves a release of radioactive material to the environment, Then direct Chemistry personnel to implement EPIP-09, Off-site Dose Calculations.

END OF SECTION 5.1

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EPIP-01 ST. LUCIE PLANT NOTE Initiating Conditions / Emergency Action Levels are applicable to all modes unless otherwise indicated.

5.2 Classifying the Event

1.

¶13 A goal of fifteen (15) minutes should be used for assessing and classifying an emergency once indications (Emergency Action Levels (EALs)) are available to Control Room Operators that an Initiating Condition (IC) has been met and/or exceeded.

A.

This goal should allow time for determination of indications (leak rate, etc.) and detailed review of Attachment 1, Emergency Classification Table.

2.

Use the best information available when working through the Emergency Classification Table. When confronted with conflicting information for which resolution is not apparent, classify the condition at the highest appropriate emergency class.

3.

If, in the judgement of the Shift Manager (SM) /Emergency Coordinator (EC), a situation is more serious than indicated by instrument readings or other parameters, Then classify the emergency condition at the more serious level (i.e., at the highest appropriate emergency class).

4.

¶5 Security Event If the Control Room is contacted by any of the following: Security, NRC, FBI or NORAD that a terrorist attack on the plant site is imminent or is occurring, Then perform the actions in the applicable Appendix to Security Force Instruction (SFI) #4, Appendix C, Unit 1 Operations Department Recommended Defensive Strategy or Appendix D, Unit 2 Operations Department Recommended Defensive Strategy.

5.

Multiple and Dual Unit Events CAUTION There can not be two concurrent declared emergency classes under the St. Lucie Plant Radiological Emergency Plan.

I A.

If one Unit is in a classified event and the same or the other Unit enters into an event where the same or lesser Emergency Class would apply, Then a new classification should NOT be declared. The event should be documented on a SNF as "Additional Information or Update" and issued as soon as practicable.

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1 EPIP-01 ST. LUCIE PLANT 5.2 Classifying the Event (continued)

5.

(continued)

B.

If one Unit is in a classified event and the other Unit enters into a more severe event in which a higher Emergency Class would apply, Then the new classification shall be declared and promptly, within the regulatory time limits, issued to the State, Counties and the NRC.

6.

¶2 If an EAL was met and the condition completely cleared prior to an emergency classification being declared, Then:

A.

Classify the event in accordance with Attachment 1.

B.

Termination of the event

1.

An event classified as an Unusual Event or Alert may be terminated at the time of declaration by the EC.

2.

An event classified as a Site Area Emergency or General Emergency may only be downgraded and/or terminated by the Recovery Manager (RM).

END OF SECTION 5.2

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1 EPIP-01 ST. LUCIE PLANT 5.3

§, T, Classification of An Event Based On Subsequent Information

1.

If subsequent information of a more detailed nature (e.g., sampling results) becomes available after the initial classification has been made, Then reclassify as appropriate.

2.

If results of a protracted review (i.e., Engineering Evaluation, CR disposition, etc.) of an event indicate that conditions were met for an Emergency Classification, and the condition has completely cleared prior to recognition of possible classification, Then notify NRC within one hour of discovery of the undeclared event.

A.

Contact Emergency Preparedness for briefing of state and local agencies.

END OF SECTION 5.3

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1[ 3 of 32 EPIP-01 ST. LUCIE PLANT ATTACHMENT I EMERGENCY CLASSIFICATION TABLE (Page 1 of 20)

CAUTION

§2 Section 1.A should not be used for a steam generator tube leak / rupture.

EVENT/CLASS 1.A.

ABNORMAL PRIMARY LEAK RATE (Page 1 of 2)

UNUSUAL EVENT Reactor Coolant System (RCS) Leakage

1. RCS leakage GREATER THAN 10 gpm as indicated by:

A.

Control Room observation QR B. Inventory balance calculation OR C.

Field observation OR

0. Emergency Coordinator judgement OQR

2. Indication of leaking RCS safety or relief valve which causes RCS pressure to drop below setpoints:

Unit 1 - 1600 psia Unit 2 - 1736 psia ALERT

§1 RCS Leakage GREATER THAN 50,pm

1. Unisolable RCS leakage as indicated by Charging/letdown mismatch greater than 50 gpm but less than available charging pump capacity.

OR

2. Unisolable measured RCS leakage indicating greater than 50 gpm but less than available charging pump capacity.

SITE AREA EMERGENCY LOCA GREATER THAN capacity of charging pumps

1. RCS leakage greater than available charging pump capacity occurring with RCS pressure above HPSI shutoff head.

OR

2.

RCS leakage greater than available makeup occurring with RCS pressure below HPSI shutoff head.

OR

3.

Loss of RCS subcooled margin due to RCS leakage (saturated conditions).

OR

4. Containment High Range Radiation Monitors indicate 7.3 X 103 R/hr (If CHRRM inoperable, Post-LOCA monitors indicate between 100 and 1000 mR/hr).

GENERAL EMERGENCY A release has occurred or is in progress resulting in:

1. Containment High Range Radiation monitor greater than 1.46 X 10' R/hr (If CHRRM inoperable, Post-LOCA monitors greater than 1000 m R/hr).

OR

2. Performance of EPIP-09 (Off-site Dose Calculations) or measured dose rates from off-site surveys indicate site boundary (1 mile) exposure levels have been exceeded as indicated by either A, B, C or D below:

A.

1000 mrem/hr (total dose rate)

B.

1000 mrem (total dose - TEDE)

C.

5000 mrem/hr (thyroid dose rate)

D.

5000 mrem (thyroid dose - CDE)

(continued on next page) 1.A.

ABNORMAL PRIMARY LEAK RATE AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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EVENT/CLASS 1.A. ABNORMAL PRIMARY LEAK RATE (Page 2 of 2)

UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY Loss of 2 of the 3 fission product barriers with imminent loss of the third (any two of the following exit and the third is imminent).

1. Fuel element failure (confirmed DEQ 1-131 activity greater than 275 pCi/mL).

AND

2. LOCA or Tube rupture on unisolable steam generator.

AND

3. Containment Integrity Breached.

NOTE Also refer to Potential Core Melt Event / Class 6.A.

1.A. ABNORMAL PRIMARY LEAK RATE AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 3 of 20)

EVENT/CLASS

1. B.

ABNORMAL PRIMARY TO SECONDARY LEAK RATE (Page 1 of 2)

UNUSUAL EVENT RCS PRI/SEC Leakage

1. Measured RCS to secondary leakage exceeds Tech. Spec.

limits.

AND

2. Secondary plant activity is detected.

ALERT Rapid gross failure of one steam generator tube (WITHIN charging pump capacity) with loss of offsite power

1. Measured RCS to secondary leakage greater than Tech. Spec.

Limits and within charging pump capacity.

AND

2. Secondary plant activity is detected.

AND

3. Loss of both Non-Vital 4.16 KV buses.

(continued on next page)

SITE AREA EMERGENCY Rapid gross failure of steam generator tubes (GREATER THAN charging pump capacity) with a loss of offsite power

1. Measured RCS to secondary leakage is greater than charging pump capacity.

AND

2. Secondary plant activity is detected.

AND

3. Loss of both Non-Vital 4.16 KV buses.

(continued on next page)

GENERAL EMERGENCY Loss of 2 of the 3 fission product barriers with imminent loss of the third (any two of the following exist and the third is imminent).

1. Fuel element failure (confirmed DEQ 1-131 activity greater than 275 pCi/mL).

AND

2.

LOCA or Tube rupture on unisolable steam generator.

AND

3.

Containment integrity breached.

NOTE Also refer to Potential Core Melt Event/Class 6.A.

1.B.

ABNORMAL PRIMARY TO SECONDARY LEAK RATE AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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EVENTICLASS 1.B. ABNORMAL PRIMARY TO SECONDARY LEAK RATE (Page 2 of 2)

UNUSUAL EVENT ALERT Rapid failure of steam generator tubes (GREATER THAN charging pump capacity)

1. Measured RCS to secondary leakage greater than charging pump capacity.

AND

2. Secondary plant activity is detected.

SITE AREA EMERGENCY

§2 Rapid failure of steam generator tube(s) (GREATER THAN charging pump capacity) with steam release in progress

1.

Measured RCS to secondary leakage greater than charging pump capacity.

AND

2.

Secondary plant activity is detected.

AND

3.

Secondary steam release in progress from affected generator (i.e., ADVs, stuck steam safety(s) or unisolable leak.)

GENERAL EMERGENCY 1.B.

ABNORMAL PRIMARY TO SECONDARYLEAK RATE AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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I EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 5 of 20)

EVENT/CLASS 1.C. LOSS OF SECONDARY COOLANT (Page 1 of 2)

UNUSUAL EVENT Rapid depressurization of secondary Diant

1. Rapid drop in either steam generator pressure to less than 600 psia.

ALERT Maior steam leak with GREATER THAN 10 qpm primary/secondary leakage

1. Rapid drop in either steam generator pressure to less than 600 psia.

AND

2. Known pri/sec leak of greater than 10 gpm.

AND

3. Secondary plant activity is detected.

Total loss of feedwater

1. No main or auxiliary feedwater flow available for greater than 15 minutes when required for heat removal.

AND

2. Steam Generator levels are less than 40% wide range.

SITE AREA EMERGENCY Major steam leak with GREATER THAN 50 qpm primary/secondary leakage and fuel damage indicated

1. Rapid drop in either steam generator pressure to less than 600 psia.

AND

2. Known pri/sec leak of greater than 50 gpm.

AND

3. Secondary plant activity is detected.

AND

4. Fuel element damage is indicated (Refer to Fuel Element Failure Event/Class 4.A).

GENERAL EMERGENCY A release has occurred or is in proaress resulting in:

1. Containment High Range Radiation monitor greater than 1.46 X 10' R/hr (If CHRRM inoperable, Post-LOCA monitors greater than 1000 mR/hr).

OR

2.

Performance of EPIP-09 (Off-site Dose Calculations) or measured dose rates from off-site surveys indicate site boundary (1 mile) exposure levels have been exceeded as indicated by either A, B, C or D below:.

A. 1000 mrem/hr (total dose rate)

B. 1000 mrem (total dose -

TEDE)

C. 5000 mrem/hr (thyroid dose rate)

D. 5000 mrem (thyroid dose-CDE)

(continued on next page)

TLOF with once-through cooling initiated

1. No main or auxiliary feedwater flow available.

AND

2. PORV(s) have been opened to facilitate core heat removal.

1.C. LOSS OF SECONDARY COOLANT AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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EVENT/CLASS 1.C. LOSS OF SECONDARY COOLANT (Page 2 of 2)

UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY Loss of 2 of the 3 fission product barriers with imminent loss of the third (any two of the following exis and the third is imminent).

1. Fuel element failure (confirmed DEQ 1-131 activity greater than 275 pCi/mL).

AND

2.

LOCA or Tube rupture on unisolable steam generator.

AND

3.

Containment Integrity Breached.

NOTE Also refer to Potential Core Melt Event/Class 6.A.

1.C. LOSS OF SECONDARY COOLANT AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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EVENT/CLASS 2.A.

UNCONTROLLED EFFLUENT RELEASE UNUSUAL EVENT Radiological effluent limits exceeded

1. Plant effluent monitor(s) exceed alarm setpoint(s).

AND

2.

Confirmed analysis results for gaseous or liquid release which exceeds ODCM limits.

NOTE If analysis is not available within one hour and it is expected that release is greater than ODCM limit, classify as UNUSUAl EVENT.

ALERT A release has occurred or is in progress that is 10 times the effluent limit

1. Plant effluent monitor(s) significantly exceed alarm setpoints.

AND

2.

Confirmed analysis results for gaseous or liquid release which exceeds 10 times ODCM limits.

NOTE If analysis is not available within one hour and it is expected that release is equal to or greater than 10 times ODCM limit, classify as ALERT.

SITE AREA EMERGENCY

§2 A release has occurred or is in progress resulting in:

1. Containment High Range Radiation Monitor greater than 7.3 X 103 R/hr (Post-LOCA monitors indicate between 100 and 1000 mR/hr, if CHRRM inoperable).

OR

2.

Measured Dose Rates or Offsite Dose Calculation (EPIP-09) worksheet values at one mile in excess of:

A. 50 mrem/hr (total dose rate) or 250 mrem/hr (thyroid dose rate) for 1/2 hour.

OR B. 500 mrem/hr (total dose rate) or 2500 mrem/hr (thyroid dose rate) for two minutes at one mile.

GENERAL EMERGENCY A release has occurred or is in progress resulting in:

1. Containment High Range Radiation monitor greater than 1.46 X 10' R/hr (If CHRRM inoperable, Post-LOCA monitors greater than 1000 mR/hr).

OR

2. Performance of EPIP-09 (Off-site Dose Calculations) or measured dose rates from off-site surveys indicate site boundary (1 mile) exposure levels have been exceeded as indicated by either A, B, C or D below A. 1000 mrem/hr (total dose rate)

B. 1000 mrem (total dose - TEDE)

C. 5000 mrem/hr (thyroid dose rate)

D. 5000 mrem (thyroid dose-CDE)

ODCM - refers to Chemistry Procedure C-200, Offsite Dose Calculation Manual (ODCM) 2.A.

UNCONTROLLED EFFLUENT RELEASE AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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EVENT/CLASS 2.B. HIGH RADIATION LEVELS IN PLANT UNUSUAL EVENT ALERT High radiation levels or high airborne contamination which indicates a severe degradation in the control of radioactive materials

1. Any valid area monitor alarm from an unplanned source with meter near or greater than full scale deflection (10' mR/hr).

OR

2. Unexpected plant iodine or particulate airborne concentration of 1000 DAC as seen in routine surveying or sampling.

OR

3. Unexpected direct radiation dose rate reading or unexpected airborne radioactivity concentration from an unplanned source in excess of 1000 times normal levels.

SITE AREA EMERGENCY GENERAL EMERGENCY 2.B. HIGH RADIATION LEVELS IN PLANT AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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EVENTICLASS

3.

FIRE EXPLOSION UNUSUAL EVENT

§z Uncontrolled fire within the Power Block lasting more than 10 minutes.

ALERT Uncontrolled fire

1. Potentially affecting safety systems.

AND

2. Requiring off-site support in the opinion of the SM/EC.

SITE AREA EMERGENCY

§2 Fire compromising the function of safety systems (e.g.. both trains rendered inoperable).

GENERAL EMERGENCY NOTE Refer to Potential Core Melt Event/Class 6.A.

SNOTE I

§2 Ex losion is defined as a rapid chemical reaction resulting in noise, heat and rapid expansion of aas.

Occurrence of an explosion within the Owner Controlled Area.

§2 Damage to structures/components in

§2 Severe damage to safe shutdown the Protected Area by explosion equipment from explosion (e.g., both which affects plant operation, trains rendered inoperable.

3.

FIRE EXPLOSION AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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EVENT/CLASS 4.A. FUEL ELEMENT FAILURE UNUSUAL EVENT Fuel element damage

1. Process monitors or area radiation surveys indicate increased letdown activity AND

2. Confirmed RCS sample indicating:

A. Coolant activity greater than the Tech Spec limit for iodine spike (Tech Spec Figure 3.4-1.).

OR B. Coolant activity greater than 100/E pCi/gram specific activity.

NOTE If analysis is not available within one hour and it is expected that activity is greater than Tech Spec limit, classify as UNUSUAL EVENT.

ALERT Fuel element failure

1. Process monitors or area radiation surveys indicate increased letdown activity and confirmed RCS Samples indicating DEQ 1-131 activity greater than or equal to 275 pCi/mL.

SITE AREA EMERGENCY Fuel element failure with in2ehinIIate core cooling

1. RCS DEQ 1-131 activity greater than or equal to 275 pCi/mL.

AND

2.

Highest CET per core quadrant indicates greater than 1 0°F superheat or 700°F.

GENERAL EMERGENCY A release has occurred or is in Progress resulting in:

1. Containment High Range Radiation monitor greater than 1.46 X 10' R/hr (If CHRRM inoperable, Post-LOCA monitors greater than 1000 mR/hr).

OR

2. Performance of EPIP-09 (Off-site Dose Calculations) or measured dose rates from off-site surveys indicate site boundary (1 mile) exposure levels have been exceeded as indicated by either A, B, C or D below:

A. 1000 mrem/hr (total dose rate)

B. 1000 mrem (total dose - TEDE)

C. 5000 mrem/hr (thyroid dose rate)

D. 5000 mrem (thyroid dose -

CDE)

NOTE If analysis is not available within one hour and it is expected that RCS activity for DEQ 1-131 is greater than 275 pCi/mL, classify as an ALERT.

4.A FUEL ELEMENT FAILURE AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

REVISION NO.:

PROCEDURE TITLE:

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8 CLASSIFICATION OF EMERGENCIES PROCEDURE NO.:

23 of 32 EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 11 of 20)

EVENTICLASS 4.B. FUEL HANDLING ACCIDENT UNUSUAL EVENT ALERT Fuel handling accident which results in the release of radioactivity to Containment or Fuel Handling Buildingq:

1. SM/EC determines that an irradiated fuel assembly may have been damaged.

AND

2. Associated area or process radiation monitors are in alarm.

SITE AREA EMERGENCY

§z Major damage to irradiated fuel in Containment or Fuel Handling Building

1. Affected area radiation monitor greater than 1000 mrem/hr.

AND

2. Damage to more than one irradiated fuel assembly.

OR Major damage resulting from uncovering of one or more irradiated fuel assemblies in the Spent Fuel Pool.

GENERAL EMERGENCY 4.8. FUEL HANDLING ACCIDENT AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

REVISION NO.:

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24 of 32 EPIP-01 ST. LUCIE PLANT ATTACHMENT I EMERGENCY CLASSIFICATION TABLE (Page 12 of 20)

EVENT/CLASS 5.A EARTHQUAKE UNUSUAL EVENT

§2 A confirmed earthquake has occurred

1. A confirmed earthquake has been experienced within the Owner Controlled Area.

OR

2. ¶4 An earthquake is detected by plant seismic monitor instruments or other means.

ALERT SITE AREA EMERGENCY GENERAL EMERGENCY

§2 A confirmed earthquake has occurred.

§2 A confirmed earthquake has occurred.

NOTE Refer to Potential Core Melt Event /

Class 6.A.

5.B. HURRICANE Hurricane Warning

1. Confirmed hurricane warning is in effect.

1.

A confirmed earthquake has occurred which registered GREATER THAN 0.05g within the Owner Controlled Area.

OR

2.

A confirmed earthquake has occurred that could or has caused trip of the turbine generator or reactor.

Hurricane warning with winds near design basis

1.

Confirmed hurricane warning is in effect and winds are expected to exceed 175 mph within the Owner Controlled Area.

NOTE At FPL's request, NOAA will provide an accurate projection of wind speeds onsite 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the onset of hurricane force winds. If that projection is not available within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of entering into the warning, classify the event using current track and wind speeds to project onsite conditions. For example, projected onsite wind speed would be less than maximum hurricane wind speed if the track is away from PSL.

1. A confirmed earthquake has occurred which registered GREATER THAN 0.1g within the Owner Controlled Area and the plant not in Cold Shutdown.

OR

2. A confirmed earthquake has occurred that has caused loss of any safety system function (e.g., both trains inoperable).

Hurricane warning with winds GREATER THAN design basis

1. Plant not at cold shutdown.

AND

2. Confirmed hurricane warning is in effect and winds are expected to exceed 194 mph within the Owner Controlled Area.

NOTE Refer to Potential Core Melt Event /

Class 6.A.

NOTE At FPL's request, NOAA will provide an accurate projection of wind speeds onsite 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the onset of hurricane force winds. If that projection is not available within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of entering into the warning, classify the event using current track and wind speeds to project onsite conditions. For example, projected onsite wind speed would be less than maximum hurricane wind speed if the track is away from PSL 5.A EARTHQUAKE 5.B. HURRICANE AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

REVISION NO.:

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8 CLASSIFICATION OF EMERGENCIES PROCEDURE NO.:

25 of 32 EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 13 of 20)

EVENT/CLASS 5.C. TORNADO 5.D. ABNORMAL WATER LEVEL UNUSUAL EVENT Notification of a tornado sighted in the Owner Controlled Area Abnormal water level conditions are expected or occurring

1. Low intake canal level of -10.5 ft.

MLW for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or more.

OR

2. Visual sightings by station personnel that water levels are approaching storm drain system capacity.

ALERT

§2 Any tornado striking the Power Block.

Flood, low water, hurricane surge or other abnormal water level conditions

1. The storm drain capacity is exceeded during hurricane surge or known flood conditions.

OR

2. Low intake canal level of -10.5 ft.

MLW for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or more with emergency barrier valves open.

SITE AREA EMERGENCY GENERAL EMERGENCY NOTE Refer to Potential Core Melt Event /

Class 6.A.

Flood, low water, hurricane surge or other abnormal water level conditions causing failure of vital equipment

1. Flood/surge water level reaching elevation +19.5 ft. (turbine building / RAB ground floor).

OR

2.

Low intake canal level has caused the loss of all ICW flow.

5.C. TORNADO 5.D. ABNORMAL WATER LEVEL AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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26 of 32 EPIP-01 ST. LUCIE PLANT EVENT/CLASS 6.A.

INCREASED AWARENESS OR POTENTIAL CORE MEL (Page 1 of 2)

ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 14 of 20)

I AtyNOTE

[Activation of the Emergency Response Facilities does not require claration of an emergency or entry into a specific emergency classification.

UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY Emergency Coordinators judgement that

§2 Emergency Coordinator's udgement that

§2 Emergency Coordinator's judgement that

§2 Emergency Coordinator's judgement that plant conditions exist which warrant plant conditions exist which have a plant conditions exist which are plant conditions exist that make release of LT increased awareness on the part of the potential to degrade the level of safety at significantly degrading in an uncontrollable large amounts of radioactivity in a short operating staff and/or local authorities the plant,

manner, period appear possible or likely. (Any core melt situation.)

1. The plant is shutdown under abnormal conditions (e.g., exceeding cooldown

1. LOCA with failure of ECCS leading to rates or primary system pipe cracks are severe core degradation or melt.

found during operation),

OR OR

2. LOCA with initially successful ECCS

2. Any plant shutdown required by and subsequent failure of containment Technical Specifications in which the heat removal systems for greater than required shutdown is not reached 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

within action limits.

OR OR

3. Total loss of feedwater followed by failure of once-through-cooling (ECCS) to adequately cool the core.

OR

4. Failure of off-site and on-site power along with total loss of feedwater makeup capability for greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

OR

5. ATWS occurs which results in core damage or causes failure of core cooling and make-up systems.

OR

6. Any major internal or external event (e.g., fire, earthquake or tornado substantially beyond design basis) which in the ECs opinion has or could cause massive damage to plant systems resulting in any of the above.

(continued on next page) 6.A.

INCREASED AWARENES

%J* ru I ILN I IAL CORE MELT AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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8 CLASSIFICATION OF EMERGENCIES 27of32 PROCEDURE NO.:

EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 15 of 20)

EVENTICLASS 6.A. INCREASED AWARENESS OR POTENTIAL CORE MELT (Page 2 of 2) 6.A. INCREASED AWARENESS OR POTENTIAL CORE MELT UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY NOTES

1. Most likely containment failure mode is melt-through with release of gases only.

Quicker releases are expected for failure of containment isolation system.

2. General Emergency must be declared for the above listed events. The likelihood of corrective action (repair of AFW pump, etc.) should not be considered.

AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

(

REVISION NO.:

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8 CLASSIFICATION OF EMERGENCIES 28Aof 32 PROCEDURE NO.:

EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 16 of 20)

EVENT/CLASS 7.A. LOSS OF POWER UNUSUAL EVENT Loss of off-site power or loss of all on-site AC power capability.

1. Loss of off-site AC power.

OR

2. Loss of capability to power at least one vital 4.16 kv bus from any available emergency diesel generator.

ALERT SITE AREA EMERGENCY

§z Station Blackout (Total Loss of AC)

§2 Station Blackout (Total Loss of AC)

GENERAL EMERGENCY NOTE Refer to Potential Core Melt Event / Class 6.A.

for GREATER THAN 15 minutes

1. Loss of off-site AC power.

AND

2. Failure of both emergency diesel generators to start or load.

Loss of all on-site DC power

1. Drop in A and B DC bus voltages to less than 70 VDC.

1.

2.

Loss of offsite AC power.

AND Sustained failure of both emergency diesel generators to start or load.

AND

3. Failure to restore AC power to at least one vital 4.16 kv bus within 15 minutes.

Loss of all vital on-site DC for oreater than 15 minutes

1. Sustained drop in A and B DC bus voltages to 70 VDC for greater than 15 minutes.

7.A. LOSS OF POWER AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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8 CLASSIFICATION OF EMERGENCIES 29Aof 32 PROCEDURE NO.:

EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 17 of 20)

EVENTICLASS 8.A. LOSS OF PLANT CONTROL FUNCTIONS UNUSUAL EVENT ALERT Loss of Plant Control Functions

1. Complete loss of any function needed for plant cold shutdown.

OR

2. Failure of the Reactor Protection System to bring the reactor subcritical when needed.

OR

3. Control Room is evacuated (for other than drill purposes) with control established locally at the Hot Shutdown Control Panel.

Loss of Shutdown Coolino

1. Complete loss of functions needed to maintain cold shutdown.

A. Failure of shutdown cooling systems, resulting in loss of cold shutdown conditions.

AND B RCS subcooling can NOT be maintained greater than 0°F.

SITE AREA EMERGENCY Critical Loss of Plant Control Functions

1. Loss of any function or system which, in the opinion of the Emergency Coordinator, precludes placing the plant in Hot Shutdown.

OR

2. Failure of the RPS to trip the reactor when needed and operator actions fail to bring the reactor subcritical.

OR

3. Control Room is evacuated (for other than drill purposes) and control cannot be established locally at the Hot Shutdown Control Panel within 15 minutes.

GENERAL EMERGENCY NOTE Refer to Potential Core Melt Event Class 6A.

8.A LOSS OF PLANT CONTROL FUNCTIONS AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

REVISION NO.:

PROCEDURE TITLE:

8 CLASSIFICATION OF EMERGENCIES PROCEDURE NO.:

EPIP-01 ST. LUCIE PLANT ATTACHMENT I EMERGENCY CLASSIFICATION TABLE (Page 18 of 20)

EVENT/CLASS 8.B. LOSS OF ALARMS I COMMUNICATION /

MONITORING UNUSUAL EVENT

§2 Significant loss of effluent monitoring capability, communications, indication and alarm panels, etc.,

which impairs ability to perform accident or emergency assessment.

1. Loss of effluent or radiological monitoring capability requiring plant shutdown.

OR

2. Loss of all primary and backup communication capability with offsite locations.

OR

3. Unplanned loss of most (greater than 75%) or all Safety System annunciators for greater than 15 minutes.

ALERT

§2 Loss of alarms

1. Unplanned loss of most (greater than 75%) or all safety system annunciators.

AND

2. Plant transient in progress.

SITE AREA EMERGENCY Loss of alarms/monitoring

1. Inability to monitor* a significant transient in progress.

GENERAL EMERGENCY

• Monitoring means loss of ERDADS, QSPDS and/or the inability to determine any one of the following:

reactivity control, core cooling, RCS status or containment integrity.

8.B. LOSS OF ALARMS /

COMMUNICATION /

MONITORING AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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PROCEDURE TITLE:

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8 CLASSIFICATION OF EMERGENCIES 3: of 32 PROCEDURE NO.:

EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 19 of 20)

EVENTICLASS 9.A. AIRCRAFT / MISSILE UNUSUAL EVENT Unusual aircraft activity

1. Aircraft crash in the Owner Controlled Area or unusual aircraft activity over facility that in the opinion of the SM/EC, could threaten the safety of the plant or personnel.

Turbine rotating component failure causing rapid plant shutdown.

Unplanned/uncontrolled toxic or flammable gas release in the Owner ALERT

§2 Aircraft/missile impact

1. Aircraft crash into the Power Block.

OR

2. Visual or audible indication of missile impact on the Power Block.

Visual indication that the turbine casing has been penetrated by blading.

Entry of toxic or flammable aas into SITE AREA EMERGENCY

§2 Damage to vital systems from aircraft/missiles

1. Aircraft crash into the Power Block damaging vital plant systems.

OR

2. Damage resulting in loss of safe shutdown equipment from any missile.

GENERAL EMERGENCY 9.B. TURBINE FAILURE 9.C. TOXIC OR FLAMMABLE GAS Controlled Area that could affect plant/personnel safety.

areas potentially affecting plant operation.

§2 Toxic or flammable gas has diffused into vital areas compromising the function of safety related equipment (e.g., both trains rendered inoperable).

9.A. AIRCRAFT/MISSILE 9.B. TURBINE FAILURE 9.C. TOXIC OR FLAMMABLE GAS AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

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8 CLASSIFICATION OF EMERGENCIES 3: of 32 PROCEDURE NO.:

EPIP-01 ST. LUCIE PLANT ATTACHMENT 1 EMERGENCY CLASSIFICATION TABLE (Page 20 of 20)

EVENTICLASS

10. SECURITY THREAT UNUSUAL EVENT A SECURITY ALERT has been called by the Security Force in response to one or more of the items ALERT A SECURITY EMERGENCY has been called by the Security Force as defined in the Safeguards Contingency Plan.

SITE AREA EMERGENCY A SECURITY EMERGENCY involving imminent occupancy of the control room or other area(s) vital to the operation of the reactor as defined in the Safeguards Contingency Plan.

GENERAL EMERGENCY A successful takeover of the plant including the Control Room or any other area(s) vital to the operation of the reactor as defined in the Safeguards Contingency Plan.

listed below.

1.

Bomb threat

2.

Attack threat LandNehicle Waterborne Airborne Insider

3.

Security Threat

4.

Protected Area intrusion attempt or breach

5.

Sabotage attempt

6.

Internal disturbance

7.

Civil disturbance

8.

Vital Area intrusion

9.

Security Force strike

10. Credible site-specific Security Threat notification

11. Extortion/Coercion/Hostage Threat against plant

12. Sniper attack

10. SECURITY THREAT AFTER CLASSIFYING, GO TO EPIP-02, DUTIES AND RESPONSIBILITIES OF THE EMERGENCY COORDINATOR

Procedure No.

ST. LUCIE PLANT EPIP-08 EMERGENCY PLAN Current Revision No.

IMPLEMENTING PROCEDURE 6A Effective Date SAFETY RELATED 01/08104

Title:

OFF-SITE NOTIFICATIONS AND PROTECTIVE ACTION RECOMMENDATIONS Responsible Department: EMERGENCY PLANNING REVISION

SUMMARY

Revision 6A - Incorporated PCR 03-3535 to put Attachment 2 in forms database. (M.

Cooper, 12/10/03)

Revision 6 - Incorporated PCR 03-2272 for CR 03-2568 to revise State Notification form.

Delete supplemental data sheet. Revise instructions for completing State form. Improve guidance relative to changing PARs (RIS 2003-12). (J.R. Walker, 08/29/03)

AND Incorporated PCR 03-1637 for MA 03-04-082 to incorporate shift communicator position.

(A. Terezakis, 08/06/03)

Revision 5 - Clarified duties, made editorial / administrative changes and removed local government radio. (J. R. Walker, 07/26/02)

Revision 4 - Clarified instructions regarding notification of rapidly degrading events. Clarified stability class instructions. Made administrative/editorial changes. (J.R. Walker, 10/11/01)

Revision FRG Review Date Approved By Approval Date SOPS 0

05130/00 R. G. West 05/31/00 DATE Plant General Manager DOCT PROCEDURE Revision FRG Review Date Approved By Approval Date DOCN EPIP-08 6A 08/28/03 R.E. Rose 08/29/03 SYS Plant General Manager COM COMPLETED N/A ITM 6A Designated Approver D. Calabrese 12/10/03 Designated Approver (Minor Correction)

REVISION NO.:

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6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 2 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT TABLE OF CONTENTS SECTION PAGE 1.0 P U R P O S E.......................................................................................................

3

2.0 REFERENCES

/ RECORDS REQUIRED / COMMITMENT DOCUMENTS........... 8 3.0 R E S P O N S IB ILIT IE S...........................................................................................

9 4.0 D E F IN IT IO N S..................................................................................................

.. 11 5.0 IN S T R U C T IO N S................................................................................................

13 5.1 State and County Notification................................................................

13 5.2 Nuclear Regulatory Commission (NRC) Notification.............................. 16 5.3 E rroneous Inform ation.............................................................................

17 APPENDICES APPENDIX A NOTIFICATIONS FROM THE AFFECTED CONTROL ROOM......

18 APPENDIX B NOTIFICATIONS FROM THE TECHNICAL SUPPORT CENTER (T S C )............................................................................................

... 2 2 APPENDIX C NOTIFICATIONS FROM THE EMERGENCY OPERATIONS FA C ILIT Y (E O F)...............................................................................

27 ATTACHMENTS ATTACHMENT 1 FLORIDA NUCLE AR PL ANT FI:IPr=IKPIrv MK'TIn'Ii TIr' I ATTACHMENT 1A ATTACHMENT 2 ATTACHMENT 3 ATTACHMENT 3A F O R M.....................................................................................

.. 3 3 DIRECTIONS FOR COMPLETING THE FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM........................ 34 DETERMINATION OF PROTECTIVE ACTION RECOMMENDATIONS (PARs)...............................................

41 NRC REACTOR PLANT EVENT NOTIFICATION W O R K S H E ET...........................................................................

46 DIRECTIONS FOR COMPLETING THE NRC REACTOR PLANT EVENT NOTIFICATION WORKSHEET....................... 48

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6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 3 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT 1.0 PURPOSE 1.1 Discussion

1.

This procedure provides information and instructions for undertaking notifications of the State Warning Point (SWP) and the Nuclear Regulatory Commission (NRC) and for determination of Protective Action Recommendations (PARS).

2.

This procedure is for use in the Control Room, Technical Support Center (TSC) and Emergency Operations Facility (EOF).

3.

Upon declaration of an emergency classification the Nuclear Plant Supervisor (NPS) assumes the duties of the Emergency Coordinator (EC).

The EC has initial responsibility for off-site notifications and PARs.

4.

Once the EOF is operational and proper turnover has been conducted, the Recovery Manager (RM) assumes responsibility for off-site notifications and PARs from the EC.

5.

At an Alert or higher level emergency, communications with the NRC transition to an open phone line from the TSC and the EOF (at a Site Area Emergency of higher level emergency).

6.

The following table illustrates which facility has a responsibility for Classification, Notification or PARs.

Control Room TSC EOF (X until EC (X when operational)

(X when operational) function transfers to the TSC)

Classifications X transfers --

X Notifications X transfers --

X transfers --

X PARs X transfers--

X transfers--

X

7.

Off-site Notification A.

Purpose of Off-Site Notifications FPL is required to notify off-site agencies in the event of any emergency that could threaten the health and safety of the public.

These notifications provide an early warning to agencies responsible for public protection.

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6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 4 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT 1.1 Discussion (continued)

7.

(continued)

NOTE The State Department of Health (Bureau of Radiation Control) may not have their office staffed on a 24-hour basis. In the event that they do not answer the Hot Ring Down (HRD) telephone, the State Warning Point (SWP) assumes responsibility for notifying their duty officer.

B.

Who Shall Be Notified State Division of Emergency Management 0

State Department of Health (Bureau of Radiation Control)

St. Lucie County Emergency Operations Center Martin County Emergency Operations Center 0

NRC

1.

State and County Notification

a.

State and local agencies are notified by using the Hot Ring Down (HRD) telephone. The HRD rings the State Warning Point (SWP). The SWP puts the other agencies on line and reduces the need for individual calls.

b.

$4 After the State Coordinating Officer (SCO) arrives in the EOF, he / she can transfer "NET Control" to the EOF. When this occurs, the Recovery Manager's PAR Briefing becomes the primary notification method for the State and Counties. The Florida Nuclear Plant Emergency Notification Form (form similar to Attachment 1) shall still be completed and provided to the SCO or his / her designee in the EOF. The EOP HRD Communicator should no longer contact the State Warning Point (SWP).

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ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT 1.1 Discussion (continued)

7.

B.

(continued)

2.

NRC Notification

a.

The NRC is notified using the Emergency Notification System (ENS) telephone.

b.

NRC notifications occur through an open line of communication in the TSC and, when operational, the EOF.

C.

Emergency Follow-up Information Requests from State and local agencies.

1.

Incoming calls should come via the SWP over the HRD phone.

If the HRD is inoperable, the SWP may use commercial telephone or ESATCOM (emergency satellite phone). If an off-site authority contacts the plant without going through the SWP, request that they contact the SWP. SWP shall verify that the agency calling is a risk county or the Department of Health (DOH) and shall notify other county and state agencies of the updated information, thus reducing the number of calls that may be directed to the plant.

2.

Long, detailed explanations of plant systems or reactor theory should be avoided. If prompted for this kind of information by the State Duty Officer, he / she should be referred to the Nuclear Division Duty Officer (NDDO).

3.

If the State or one of the Counties provides either the TSC or EOF with new or pertinent information, Then bring that information to the attention of the EC or EC Assistant /

Logkeeper in the TSC or the RM or the RM OPS Advisor I Logkeeper in the EOF.

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6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 6 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT 1.1 Discussion (continued)

8.

Protective Action Recommendations A.

Protective actions for the general public are ordinarily NOT required prior to declaration of a General Emergency. It is possible however, that due to unusually stable and constant meteorological conditions, protective actions could be recommended at a Site Area Emergency based on projected doses. This is the exception rather than the rule.

Protective actions for the general public are required to be recommended if a General Emergency is declared. Initial Protective Action Recommendations (PARs) are normally based on plant conditions. This would NOT be true if the General Emergency was declared based on off-site dose (either measured or projected) or a Security Emergency (per the Security Plan). The predetermined minimum PARs (based on plant conditions) are as given below.

B.

General Emergency - Minimum PARs

1.

In any case where a GENERAL EMERGENCY has been declared, the minimum PAR shall be:

Shelter all people within a 2-mile radius and out to 5 miles in the sectors affected. The sectors affected are at least three, the downwind sector plus the two adjacent sectors.

2.

If a GENERAL EMERGENCY has been declared due to actual or projected severe core damage, the minimum PAR shall be:

Evacuate all people within a 2-mile radius from the plant and out to 5 miles in the sectors affected. Shelter all people in the remaining sectors from 2 to 5 miles and from 5 to 10 miles from the plant.

3.

If a GENERAL EMERGENCY has been declared due to loss of physical control of the plant to intruders, including the Control Room or any other area(s) vital to the operation of the reactor system (as defined in the Security Plan), the minimum PAR shall be:

Evacuate all people within a 2-mile radius from the plant and out to 5 miles in the sectors affected. Shelter all people in the remaining sectors from 2 to 5 miles and from 5 to 10 miles from the plant.

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ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT 1.1 Discussion (continued)

8.

(continued)

C.

Once a release of radioactive material occurs, dose assessment should be utilized when evaluating PARs. The final determination of the PAR should consider all available information including off-site dose projections, plant conditions and field monitoring data. The most conservative recommendation shall be made.

D.

If it is anticipated that a PAR threshold will be exceeded, DO NOT wait until the threshold is exceeded to make that PAR.

E.

%12 Conditions (plant information, dose projections and field monitoring results) are to be continually assessed and PARs expanded, as necessary, to ensure that adequate (most conservative) PARs are issued.

F.

¶12 Previously issued PARs, unless found to be less conservative, are to remain in effect until the threat is fully under control and the event is being de-escalated.

G.

112 Only State and County officials can implement, change and/or terminate protective actions.

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6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 8 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT

2.0 REFERENCES

/ RECORDS REQUIRED / COMMITMENT DOCUMENTS NOTE One or more of the following symbols may be used in this procedure:

§ Indicates a Regulatory commitment made by Technical Specifications, Condition of License, Audit, LER, Bulletin, Operating Experience, License Renewal, etc. and shall NOT be revised without Facility Review Group review and Plant General Manager approval.

¶ Indicates a management directive, vendor recommendation, plant practice or other non-regulatory commitment that should NOT be revised without consultation with the plant staff.

P Indicates a step that requires a sign off on a data sheet.

2.1 References

1.

St. Lucie Plant Updated Final Safety Analysis Report (UFSAR) Unit 1 and Unit 2

2.

St. Lucie Plant Technical Specifications Unit 1 and Unit 2

3.

§1 St. Lucie Plant Radiological Emergency Plan (E-Plan)

4.

E-Plan Implementing Procedures (EPIP 00 - 13)

5.

St. Lucie Plant Emergency Response Directory (ERD)

6.

QI-1 7-PSL-1, Quality Assurance Records 2.2 Records Required

1.

All PAR worksheets and notifications forms (all attachments) shall be maintained in plant files in accordance with QI-1 7-PSL-1.

2.3 Commitment Documents

1.

¶J PMAI PM96-04-165, "ITR 96-006" (Unusual Event Declared Due to Dropped Rod)

2.

¶2 PMAI PM96-09-185, Condition Report CR-96-1750 (Off-site Notification Using Commercial Phone)

3.

¶3 NRC Inspection Report 91-01, Closure of IFIs 89-31-03 and 89-31-01

4.

¶4 Condition Report CR-00-0428 (Evaluated Exercise Critique)

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6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 9 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT 2.3 Commitment Documents (continued)

5.

16 PMAI PM96-05-233 (Off-site Notification Process)

6.

%7 PMAI PM99-09-016 (PARs Based on FMT Data, Completion of NRC Notification Form)

7.

18 NUREG-1022, Event Reporting Guidelines 10 CFR 50.72 and 50.73, Section 4.2.4, ENS Event Notification Worksheet (NRC Form 361).

8.

19 Condition Reports CR-01-0726 and CR-01 -0742 (NOUEs Associated with SDC During SL1-17 Outage)

9.

T1o Condition Report CR-01-0389 (Alternate Met Data Source)

10.

T11 Condition Report CR-02-0333 (Role of Duty Call Supervisor)

11.

¶12 Condition Report CR-03-2568 (Response to RIS 2003-12 Regarding PARs) 3.0 RESPONSIBILITIES 3.1 Emergency Coordinator - Responsible for classifications, notifications and PARs.

3.2 Recovery Manager - Responsible for notifications and PARs.

3.3

¶ii Duty Call Supervisor-Assists the EC as a phonetalker.

3.4 TSC EC Assistant / Logkeeper or TSC OPS Coordinator - Prepares notification forms (Attachment 1, Florida Nuclear Plant Emergency Notification Form, and if necessary, Attachment 3, NRC Reactor Plant Event Notification Worksheets) for EC approval when the TSC is operational.

3.5 EOF RM OPS Advisor / Logkeeper - Prepares notification forms (Attachment 1 and if necessary, Attachment 3) for RM approval when the EOF is operational.

3.6 TSC HRD Communicator - Assists the TSC EC Assistant / Logkeeper or TSC OPS Coordinator with notification form preparation and makes calls to complete notifications to the SWP.

3.7 EOF HRD Communicator - Assists the EOF RM OPS Advisor with form preparation and makes calls to complete notifications to the SWP and the SCO following transfer of Net Control by the Division of Emergency Management (DEM).

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6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 10 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT 3.8 TSC Chemistry Supervisor (in his absence, TSC Dose Assessor) - Assists the EC with radiological dose assessment data and PARS.

3.9 EOF HP Manager (in his absence, EOF Dose Assessor) - Assists the RM with radiological dose assessment data and PARS.

3.10 TSC Supervisor - Oversees communications performed by the TSC Communicators (HRD, ENS, Health Physics Network (HPN), Sound-Powered Phonetalker, EOF and Field Monitoring Team).

3.11 EOF Nuclear Licensing Manager - Oversees EOF communications performed by the EOF Communicators (HRD, ENS, HPN and TSC).

3.12 Information Services - Maintains user copies, in the Unit 1 and Unit 2 Control Rooms, of the following checklist and supporting attachments for making notifications and developing Protective Action Recommendations:

Appendix A, Notifications from the Affected Control Room

• - Florida Nuclear Plant Emergency Notification Form

• A - Directions for Completing the Florida Nuclear Plant Emergency Notification Form 0 - Determination of Protective Action Recommendations (PARs)

• - NRC Reactor Plant Event Notification Worksheet

• A - Directions for Completing the NRC Reactor Plant Event Notification Worksheet 3.13 Shift Communicator-Assists the Nuclear Plant Supervisor/Emergency Coordinator in making emergency off-site notifications and performing other activities, as directed.

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6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 11 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT 4.0 DEFINITIONS 4.1 Conservative - Means more extensive or comprehensive action under a given set of circumstances to provide a greater measure of safety. For example, evacuation is more conservative than sheltering.

4.2 Emergency - Any off-normal event or condition which is classified into one of the four emergency classes (Unusual Event, Alert, Site Area Emergency, or General Emergency) by the NPS in accordance with EPIP-01, Classification of Emergencies.

4.3 Emergency Coordinator (EC) - The title initially assumed by the NPS, until relieved by plant management through proper turnover, in the event of plant conditions that trigger implementation of the Emergency Plan. The EC is responsible for notifying off-site authorities, emergency responders both inside and outside the company and has full authority and responsibility for on-site emergency response actions. The EC is also responsible for Protective Action Recommendations during the initial stages of an emergency.

4.4 Florida Nuclear Plant Emergency Notification Form - A predetermined format used by nuclear power plants throughout the State for notification and local authorities.

4.5 Operational (status for an emergency facility) - The mandatory minimum staff is present and the facility has taken responsibility for its procedurally assigned functions.

4.6 Protective Action Recommendations (PARs) - Recommendations, for action instructions to protect the public, made by the Emergency Coordinator or Recovery Manager to State and County officials. FPL may recommend No Action, Sheltering or Evacuation.

4.7 Recovery Manager (RM) - A designated company officer or senior manager, who will have responsibility for the direction and control of the EOF. He / she has the authority to establish policy and to expend funds necessary to cope with emergency situations that trigger the implementation of the Emergency Plan.

4.8 Release (during any declared emergency)

1.

Any effluent monitor increase of (approximately) 10 times or one decade above pre-transient values.

OR

2.

Health Physics detecting airborne radioactivity levels in excess of 25%

derived air concentration (DAC) outside of plant buildings due to failure of equipment associated with the declared emergency.

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6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 12 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT 4.9 Shift Communicator - A specific shiftly designated individual trained and qualified to assist the Nuclear Plant Supervisor/Emergency Coordinator in the control room in making emergency off-site notifications, and performing other activities as directed.

4.10 State Notification Form (SNF) - Less formal, more concise expression used in lieu of Florida Nuclear plant Emergency Notification Form.

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6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 13 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT 5.0 INSTRUCTIONS 5.1 State and County Notification

1.

Time Limits A.

Notification shall be initiated within 15 minutes of any of the following:

1.

Recognition of entry into the Emergency Plan.

2.

Escalation in Emergency Class.

3.

De-escalation of the Emergency Class.

4.

Protective Action Recommendation.

5.

Change in Protective Action Recommendation.

B.

Notification shall be initiated within 60 minutes of any of the following:

1.

At an Alert or higher Emergency Class, the time of the last update (unless a different frequency has been agreed to by the off-site agencies as during a hurricane).

2.

A radiological release has been initiated.

3.

A radiological release has been terminated.

4.

A significant change in plant conditions has occurred (e.g., loss or restoration of off-site power or major plant equipment).

5.

Termination of the emergency.

r mI-Vl0lUN Nu.:

P-ROCEURE TITLE:

6A OFF-SITE NOTIFICATIONS AND PROTECTIVE PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT 5.1 State and County Notification (continued)

2.

Forms Required for Notifications CAUTION Notifications require the use of a form similar to Attachment 1, Florida NuearPlant Emergency Notification Form.

A.

Notifications with 15 minute time limits shall be made using a form similar to Attachment 1, Florida Nuclear Plant Emergency Notification Form.

B.

Notifications with 60 minute time limits shall be made using a form similar to Attachment 1, Florida Nuclear Plant Emergency Notification Form.

3.

Special instructions due to extraordinary circumstances.

A.

If Emergency Class escalation is necessary due to rapidly degrading conditions, Then provide the State and County authorities with the initial notification information by transmitting lines 1-6, at a minimum, of the SNF and terminate the phone call by stating that a new notification form will be provided within 15 minutes.

CAUTION There can not be two concurrent declared emergency classes under the St. Lucie Plant Radiological Emergency Plan.

I B.

If one Unit is in a classified event and the same or the other Unit enters into an event where the same or lesser Emergency Class would apply, Then a new classification should NOT be declared. The event should be documented on a SNF as "Additional Information or Update" and issued as soon as practicable.

C.

If one Unit is in a classified event and the other Unit enters into a more severe event in which a higher Emergency Class would apply, Then the new classification shall be declared and promptly, within the regulatory time limits, issued to the State, Counties and the NRC.

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6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 15 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT 5.1 State and County Notification (continued)

4.

]4 Transfer of NET Control A.

The State Coordinating Officer (SCO) can transfer the control of Hot Ring Down (HRD) NET from the State Warning Point (SWP) to the EOF. When this occurs;

1.

The RM shall do face to face communication to satisfy off-site notification requirements for the State and Counties. Calls to the SWP are no longer necessary.

2.

The Florida Nuclear Plant Emergency Notification Form (Attachment 1) shall continue to be filled out.

3.

Completed notification forms are to be provided to the SCO or his / her designee in the EOF.

END OF SECTION 5.1

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6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 16 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT 5.2 Nuclear Regulatory Commission (NRC) Notification

1.

Time Limits NOTE Notification of the NRC is expected immediately after notification of State and local agencies. The one-hour time limit in 10 CFR 50.72 (a)(3) is to ensure timely NRC notification in cases where notification of State and local agencies is delayed or prolonged.

A.

The licensee shall notify the NRC immediately after notification of the appropriate State or local agencies and not later than one hour after the time the licensee declares one of the Emergency Classes (10 CFR 50.72 (a)(3)).

2.

Special Instructions A.

Initial notification to the NRC using the Emergency Notification System (ENS) (usually done from the Control Room) should use, NRC Reactor Plant Event Notification Worksheet.

B.

At an Alert or higher emergency class, the NRC will want to establish an open line of communication with the Control Room, utilizing an ENS conference bridge tying in the licensee with NRC Headquarters and region personnel. Once the Technical Support Center (TSC) is operational, the Control Room should transfer responsibility for NRC communications to the TSC.

C.

The Emergency Operations Facility (EOF) should join the TSC on the ENS conference bridge and take the lead for NRC communications.

D.

The TSC and EOF should also utilize the Health Physics Network (HPN) line in a manner similar to the ENS (i.e., establish a conference bridge with the NRC).

E.

Both the ENS and HPN Communicators in both facilities should keep logs of information transmitted and received from the NRC in accordance with procedures.

END OF SECTION 5.2

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6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 17 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT 5.3

¶T Erroneous Information

1.

If erroneous information is transmitted to off-site agencies and the error is discovered prior to event termination, a correction should be provided in an update. The need for and urgency of providing the update is dependent upon the importance of the error.

2.

If erroneous information is transmitted to off-site agencies and the error is discovered after event termination, the Licensing Department should be consulted to determine the need and method for contacting the off-site agencies with corrected information.

END OF SECTION 5.3

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ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT APPENDIX A NOTIFICATIONS FROM THE AFFECTED CONTROL ROOM (Page 1 of 4)

INITIAL CAUTION

§1 Notification of State and local agencies shall be made as soon as practicable within 15 minutes of declaration of an Emergency Class.

• ¶3 A new Florida Nuclear Plant Emergency Notification Form shall be completed for all updates.

NOTE

¶9

1.

Completion of this checklist requires the following Attachments (all from EPIP-08): - Florida Nuclear Plant Emergency Notification Form A - Directions for Completing the Florida Nuclear Plant Emergency Notification Form - Determination of Protective Action Recommendations (PARs) - NRC Reactor Plant Event Notification Worksheet A - Directions for Completing the NRC Reactor Plant Event Notification Worksheet

2.

Checklist Part 1 is for State Warning Point notification.

3.

Checklist Part 2 is for NRC notification.

1.

State Warning Point Notification A.

Prepare the Florida Nuclear Plant Emergency Notification Form (form similar to Attachment 1) in accordance with Attachment 1A, Directions for Completing the Florida Nuclear Plant Emergency Notification Form.

B.

Emergency Coordinator (EC) approval.

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6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 19 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT APPENDIX A NOTIFICATIONS FROM THE AFFECTED CONTROL ROOM (Page 2 of 4)

1.

(continued)

INITIAL NOTE

1.

Primary notification method to the State Warning Point (SWP) is to use the Hot Ring Down (HRD) phone.

2.

If the HRD is out-of-service, alternate notification methods are provided in Section E, below.

C.

Using the State HOT RING DOWN (HRD) Phone, dial 100.

D.

Hold down the button on the handset while talking. This must be done each time you talk. Release the button in order to listen.

When the State Duty Officer answers, announce "This is St. Lucie Nuclear Plant [as applicable (Unit 1, 2)] with an emergency message. I am standing by to transmit the Florida Nuclear Plant Emergency Notification Form when you are ready to copy." Allow the Duty Officer to contact St. Lucie County, Martin County and the Bureau of Radiation Control prior to transmitting the information from the notification form. When the parties are on line, provide the information slowly (e.g., in three word intervals) and deliberately, providing time for the information to be written down.

E.

Alternate Notification Methods (in order of priority) 0)

NOTE Use of the commercial telephone as an alternate notification method requires callback verification from the State Warning Point. Use of ESATCOM as an alternate notification method should include a callback verification number if available (e.g., cellular phone).

1.

Alternate 1 - Commercial Phone

a.

Call the State Warning Point using the phone number in the St. Lucie Plant Emergency Response Directory (ERD). Announce "This is St. Lucie Nuclear Plant [as applicable (Unit 1 / 2)] with an emergency declaration. My callback number is

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ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT APPENDIX A NOTIFICATIONS FROM THE AFFECTED CONTROL ROOM (Page 3 of 4)

1.

E.

1.

(continued)

INITIAL

b.

Hang up the phone and standby for the callback.

When the State Warning Point gives the go-ahead, provide the information from the Florida Nuclear Plant Emergency Notification Form.

c.

¶12 Request callback from the State Warning Point to verify that they notified St. Lucie County, Martin County and the Bureau of Radiation Control.

2.

Alternate 2 - ESATCOM NOTE Use ESATCOM only if Alternate 1 - commercial phone is not available.

a.

Hold down the "push-to-talk" button on the handset and wait 3-5 seconds to hear a beep before you start talking. This must be done each time you talk.

b.

Announce "State Warning Point, this is St. Lucie Nuclear Plant [as applicable (Unit 1 / 2)] with an emergency declaration." Then release the "push-to-talk" button in order to listen.

c.

When the State Warning Point acknowledges, announce "State Warning Point, this is St. Lucie Nuclear Plant [as applicable (Unit 1 / 2)] declaring a

/ an (classification), repeat (classification). I am standing by to transmit Florida Nuclear Plant Emergency Notification Form information when you are ready to copy. When the State Warning Point gives the go-ahead, provide the information from the Florida Nuclear Plant Emergency Notification Form.

d.

Announce "St. Lucie clear' at the end of the conversation.

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6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 21 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT APPENDIX A NOTIFICATIONS FROM THE AFFECTED CONTROL ROOM (Page 4 of 4)

INITIAL CAUTION Notification of the NRC is expected immediately after notification of State and local agencies. The one hour time limit in 10 CFR 50.72 (a)(3) is to ensure timely NRC notification in cases where notification of State and local agencies is delayed or prolonged.

2.

§1 NRC Notification A.

Prepare the NRC Reactor Plant Event Notification Worksheet (form similar to Attachment 3) in accordance with Attachment 3A, Directions for Completing the NRC Reactor Plant Event Notification Worksheet.

B.

EC approval.

NOTE

1.

Primary notification method to the NRC is to use the Emergency Notification System (ENS) phone.

2.

If the ENS is out-of-service an alternate notification method is provided in Section D, below.

C.

Transmit the form by dialing one of the numbers shown on the phone or in the Emergency Response Directory (ERD).

D.

Alternate Notification Method

1.

If the ENS is out-of-service, Then use a commercial phone to accomplish the above.

END OF APPENDIX A

REVISION NO.:

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6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 22 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT I

APPENDIX B NOTIFICATIONS FROM THE TECHNICAL SUPPORT CENTER (TSC)

(Page 1 of 5)

INITIAL CAUTION

§1 Notification of State and local agencies shall be made as soon as practicable within 15 minutes of declaration of an Emergency Class.

¶3 A new Florida Nuclear Plant Emergency Notification Form shall be completed for all updates.

D NOTE Checklist Part 1 is for HRD Communications.

ECheckklist Part 2 is for ENS Communications.

State Warning Point Notification A.

Prepare the Florida Nuclear Plant Emergency Notification Form (form similar to Attachment 1) in accordance with Attachment 1A, Directions for Completing the Florida Nuclear Plant Emergency Notification Form.

B.

Verify the Emergency Coordinator (EC) approval.

NOTE

1.

Primary notification method to the State Warning Point (SWP) is to use the Hot Ring Down (HRD) phone.

2.

If the HRD is out-of-service, alternate notification methods are provided in Section E, below.

I C.

Using the State HOT RING DOWN (HRD) Phone, dial 100.

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ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT APPENDIX B NOTIFICATIONS FROM THE TECHNICAL SUPPORT CENTER (TSC)

(Page 2 of 5)

1.

(continued)

INITIAL D.

Hold down the button on the handset while talking. This must be done each time you talk. Release the button in order to listen.

When the State Duty Officer answers, announce "This is St. Lucie Nuclear Plant Technical Support Center with an emergency message. I am standing by to transmit the Florida Nuclear Plant Emergency Notification Form when you are ready to copy." Allow the Duty Officer to contact St. Lucie County, Martin County and the Bureau of Radiation Control prior to transmitting the information from the notification forms. When the parties are on line, provide the information slowly (e.g., in three word intervals) and deliberately, providing time for the information to be written down.

E.

Alternate Notification Methods (in order of priority)

NOTE Use of the commercial telephone as an alternate notification method requires callback verification from the State Warning Point. Use of ESATCOM as an alternate notification method should include a callback verification number if available (e.g., cellular phone).

1.

Alternate 1 - Commercial Phone

a.

Call the State Warning Point using the phone number in the St. Lucie Plant Emergency Response Directory (ERD). Announce "This is St. Lucie Nuclear Plant Technical Support Center with an emergency declaration. My callback number is

b.

Hang up the phone and standby for the callback.

When the State Warning Point gives the go-ahead, provide the information from the Florida Nuclear Plant Emergency Notification Form.

c.

¶12 Request callback from the State Warning Point to verify that they notified St. Lucie County, Martin County and the Bureau of Radiation Control.

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(Page 3 of 5)

1.

E.

(continued)

INITIAL

2.

Alternate 2 - ESATCOM NOTE Use ESATCOM only if Alternate 1 - commercial phone is not available.

a.

Hold down the "push-to-talk" button on the handset and wait 3-5 seconds to hear a beep before you start talking. This must be done each time you talk.

b.

Announce "State Warning Point, this is St. Lucie Nuclear Plant Technical Support Center with an emergency declaration." Then release the "push-to-talk" button in order to listen.

c.

When the State Warning Point acknowledges, announce "State Warning Point, this is St. Lucie Nuclear Plant Technical Support Center declaring a / an (classification), repeat (classification). I am standing by to transmit the Florida Nuclear Plant Emergency Notification Form when you are ready to copy. When the State Warning Point gives the go-ahead, provide the information from the Florida Nuclear Plant Emergency Notification Form.

d.

Announce "St. Lucie clear" at the end of the conversation.

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ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT APPENDIX B NOTIFICATIONS FROM THE TECHNICAL SUPPORT CENTER (TSC)

(Page 4 of 5)

INITIAL CAUTION Notification of the NRC is expected immediately after notification of State and local agencies. The one-hour time limit in 10 CFR 50.72 (a)(3) is to ensure timely NRC notification in cases where notification of State and local agencies is delayed or prolonged.

NOTE

1.

Primary notification method to the NRC is to use the Emergency Notification System (ENS) phone.

2.

If the ENS is out-of-service, an alternate notification method is provided in Section B, below.

2.

§1 NRC Notification A.

Choose and complete the appropriate steps, below:

1.

If the NRC Reactor Plant Event Notification Worksheet has NOT previously been transmitted from the Control Room, Then request that the EC Assistant / Logkeeper prepare the form.

2.

Verify EC approval.

3.

Transmit the form by dialing one of the numbers shown on the phone or in the Emergency Response Directory (ERD),

then GO TO the next step to establish an open line of communication with the NRC.

OR

4.

If the NRC Reactor Plant Event Notification Worksheet has previously been transmitted by the Control Room, Then initiate an open line of communication with the NRC by dialing one of the numbers shown on the phone or in the ERD and request to be placed on the Conference Bridge with the NRC.

5.

As requested, provide information to the NRC.

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ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT APPENDIX B NOTIFICATIONS FROM THE TECHNICAL SUPPORT CENTER (TSC)

(Page 5 of 5)

2.

(continued)

INITIAL B.

Alternate Notification Method

1.

If the ENS is out-of-service, Then use a commercial phone to accomplish the above.

END OF APPENDIX B

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ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT APPENDIX C NOTIFICATIONS FROM THE EMERGENCY OPERATIONS FACILITY (EOF)

(Page 1 of 6)

INITIAL CAUTION

§1 Notification of State and local agencies shall be made as soon as practicable within 15 minutes of declaration of Emergency Class or change in Protective Action Recommendation (PAR).

¶3 A new Florida Nuclear Plant Emergency Notification Form shall be completed for all updates.

NOTE Checklist Part 1 is for HRD Communications.

• Checklist Part 2 is for ENS Communications.

1.

State Warning Point Notification A.

Prepare the Florida Nuclear Plant Emergency Notification Form (form similar to Attachment 1) in accordance with Attachment 1A, Directions for Completing the Florida Nuclear Plant Emergency Notification Form.

B.

Verify the Recovery Manager (RM) approval.

REVISION NO.:

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ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT APPENDIX C NOTIFICATIONS FROM THE EMERGENCY OPERATIONS FACILITY (EOF)

(Page 2 of 6)

1.

(continued)

INITIAL NOTE

1.

Primary notification method to the State Warning Point (SWP) is to use the Hot Ring Down (HRD) phone.

2.

If the HRD is out-of-service, alternate notification methods are provided in Section D, below.

3.

State and County representatives means Florida Division of Emergency Management (DEM), Florida Department of Health (DOH),

St. Lucie County Department of Public Safety (DPS) and Martin County Department of Emergency Services (DES).

4.

Notification forms means the Florida Nuclear Plant Emergency Notification Form.

C.

Choose and complete the appropriate step below:

1.

If State and County representatives are NOT co-located with the FPL Emergency Response Organization (ERO) in the EOF, Then call the SWP and transmit the notification forms. To contact the SWP, dial 100. Hold down the button on the handset while talking. This must be done each time you talk. Release the button in order to listen.

When the State Duty Officer answers, announce "this is St. Lucie Nuclear Plant Emergency Operations Facility with an emergency message. I am standing by to transmit the Florida Nuclear Plant Emergency Notification Form when you are ready to copy." Allow the Duty Officer to contact the Bureau of Radiation Control, St. Lucie County DPS and Martin County DES prior to transmitting the information from the notification forms. When the parties are on line, transmit the information slowly, (e.g., in three word intervals) and deliberately, providing time for the information to be written down.

0)

OR

REVISION NO.:

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ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT APPENDIX C NOTIFICATIONS FROM THE EMERGENCY OPERATIONS FACILITY (EOF)

(Page 3 of 6)

1.

C.

(continued)

INITIAL

2.

If State and County representatives are co-located with the FPL ERO in the EOF and the State Coordinating Officer (SCO) has NOT assumed Net Control, Then call the SWP and transmit the notification forms - "Time of Contact" corresponds to the start time of the Recovery Manager's Protective Action Recommendation (PAR) Briefing. To contact the SWP, dial 100. Hold down the button on the handset while talking. This must be done each time you talk. Release the button in order to listen. When the State Duty Officer answers, announce "this is St. Lucie Nuclear Plant Emergency Operations Facility with an emergency message. I am standing by to transmit the Florida Nuclear Plant Emergency Notification Form when you are ready to copy." Allow the Duty Officer to contact the Bureau of Radiation Control, St. Lucie County DPS and Martin County DES prior to transmitting the information from the notification forms. When the parties are on line, transmit the information slowly, (e.g., in three word intervals) and deliberately, providing time for the information to be written down.

OR

3.

If State and County representatives are co-located with the FPL ERO in the EOF and the SCO has transferred Net Control to the EOF, Then the SWP is not called (completed notification forms are given to the SCO - may be accomplished by the RM or RM OPS Advisor / Logkeeper).

D.

Alternate Notification Methods (in order of priority)

NOTE Use of the commercial telephone as an alternate notification method requires callback verification from the State Warning Point. Use of ESATCOM as an alternate notification method should include a callback verification number if available (e.g., cellular phone).

1.

Alternate 1 - Commercial Phone

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ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT APPENDIX C NOTIFICATIONS FROM THE EMERGENCY OPERATIONS FACILITY (EOF)

(Page 4 of 6) 1 D.

1.

(continued)

INITIAL

a.

Call the State Warning Point using the phone number in the St. Lucie Plant Emergency Response Directory (ERD). Announce "This is St. Lucie Nuclear Plant Emergency Operations Facility with an emergency declaration. My callback number is

b.

Hang up the phone and standby for the callback.

When the State Warning Point gives the go-ahead, provide the information from the Florida Nuclear Plant Emergency Notification Form.

c.

¶12 Request callback from the State Warning Point to verify that they notified St. Lucie County, Martin County and the Bureau of Radiation Control.

2.

Alternate 2 - ESATCOM NOTE Use ESATCOM only if Alternate 1 - commercial phone is not available.

a.

Hold down the "push-to-talk" button on the handset and wait 3-5 seconds to hear a beep before you start talking. This must be done each time you talk.

b.

Announce "State Warning Point, this is St. Lucie Nuclear Plant Emergency Operations Facility with an emergency declaration." Then release the "push-to-talk" button in order to listen.

c.

When the State Warning Point acknowledges, announce "State Warning Point, this is St. Lucie Nuclear Plant Emergency Operations Facility declaring a / an (classification), repeat (classification).

I am standing by to transmit the Florida Nuclear Plant Emergency Notification Form when you are ready to copy." When the State Warning Point gives the go-ahead, provide the information from the Florida Nuclear Plant Emergency Notification Form.

REVISION NO.:

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6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 31 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT APPENDIX C NOTIFICATIONS FROM THE EMERGENCY OPERATIONS FACILITY (EOF)

(Page 5 of 6)

1.

D.

2.

(continued)

d.

Announce "St. Lucie clear" at the end of the conversation.

INITIAL CAUTION Notification of the NRC is expected immediately after notification of State and local agencies. The one-hour time limit in 10 CFR 50.72 (a)(3) is to ensure timely NRC notification in cases where notification of State and local a2gencies is delayed or prolonged.

2.

§1 NRC Notification NOTE

1.

Primary notification method to the NRC is to use the Emergency Notification System (ENS) phone.

2.

If the ENS is out-of-service, an alternate notification method is provided in Section B, below.

A.

Choose and complete the appropriate steps, below:

1.

If the NRC Reactor Plant Event Notification Worksheet has NOT previously been transmitted from either the Control Room or Technical Support Center (TSC), Then request that the RM OPS Advisor prepare the form.

2.

Verify RM approval.

3.

Transmit the form by dialing one of the numbers shown on the phone or in the Emergency Response Directory (ERD),

then GO TO the next step to establish an open line of communication with the NRC.

OR

4.

If the NRC Reactor Plant Event Notification Worksheet has previously been transmitted by either the Control Room or the TSC, Then initiate an open line of communication with the NRC by dialing one of the numbers shown on the phone or in the ERD and request to be placed on the Conference Bridge with the NRC and the St. Lucie TSC.

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6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 32 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT APPENDIX C NOTIFICATIONS FROM THE EMERGENCY OPERATIONS FACILITY (EOF)

(Page 6 of 6)

2.

A.

(continued)

INITIAL

5.

Take the lead in providing information to the NRC.

B.

Alternate Notification Method

1.

If the ENS is out-of-service, Then use a commercial phone to accomplish the above.

END OF APPENDIX C

REVISION NO.:

PROCEDURE TITLE:

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6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 33 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT ATTACHMENT 1 FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM (Page 1 of 1)

On-line Verification:

1.

A.

C3 THISI C1 SWP/DEM

[] St. Lucie County C] Martin County S A DRILL

2.

A.

Date:

/

/

D.

Message Number. __

3.

Site:

A. El Crystal River Unit 3 D. El Turkey Point Unit 3

4.

Emergency Classification:

A.

B.

5.

A. El Emergency Declaration:

6.

Reason for Emergency Declaration:'

B. 0l THIS IS AN EMERGENCY B. Contact Time: __

C. Reported by: (Name)

E.

Reported from: [] Control Room El TSC El EOF B. 0l St. Lucie Unit 1 C. 0l St. Lucie Unit 2 E. [I Turkey Point Unit 4 El Notification of Unusual Event o Alert B.

El Emeroency Termination:

C. [I Site Area Emergency D. [I General Emergency Date:

/

/

Time:

A.

El EAL Number OR B. []

Description:

7.

Additional Information or Update:

A.

E] None OR B. El 8.

9.

10.

Weather Data:

A. Wind direction from __

degrees B. Downwind Sectors Affected:

Release Status:

A. 0l None (Go to Item 11)

B. El Is occurrng C.

Release Sionificance Categorv (at the Site Boundary):

0 Has occurred, but stopped A.

0l Information not available at this time.

B.

0l Release within normal operating limits (!5 3.5 E-1 Ci/sec noble gas,

• 4.6 E-5 Ci/sec iodine)

C.

0l Non-Significant Fraction of PAG Range (release is> normal limits and 500 mrem TEDE and 1000 mrem CDE)

D.

0l PAG Range (>_500 mrem TEDE orŽ_ 1000 mrem CDE)

11.

Utility Recommended Protective Actions:

A.

El No recommended actions at this time.

B.

El The utility recommends the following protective actions:

El Miles No Action Sectors Evacuate Sectors Shelter Sectors 0-2 2-5 5-10 OR Shelter Zones / Areas:

Evacuate Zones / Areas:

C.

Consider Issuance of KI:

El Yes [] No if form is completed in the Control Room, go to Item 15. If completed in the TSC or EOF, continue with item 12.

12.

Plant Conditions:

A. Reactor Shutdown? 0l Yes [I No B. Core Adequately Cooled? El Yes [] No C. Containment Intact? El Yes El No

0. Core Condition: 0l Stable 0l Degrading 13.

14.

Weather Data:

A. Wind Speed __

mph B. Stability Class Additional Release Information: 0l N/A OR A. El Noble Gases __

Curies per second B. El todines __

Cunes per second C. Airbome: Date Started

/

I Time Started -

Date Stopped 1

/

D. Liquid:

Date Started

/

I Time Started Date Stopped

/

/

Distance Proiected Thyroid Dose (CDEt for 1 Hour Proiected Total Dos 1 Mile (Site Boundary)

E.

mrem F.

2 Miles G.

mram H.

5 Miles I.

mrem J.

10 Miles K.

mrem L.

lime Stopped --

Time Stopped __

e (TEDE) for 1 Hour mrem mrem mrem mrem EC or RM Approval Signature:

Date:

I

/

Date:

/

/

Time: __

Time:

15.

Message Received By: Name:

If emergency class escalation is known to be necessary and a new notification form will be transmitted within 15 minutes, then you may go to line 15.

PSL-F070 Effective Date: 08/29/03 END OF ATTACHMENT 1

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6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 34 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT

¶6 ATTACHMENT 1A DIRECTIONS FOR COMPLETING THE FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM (Page 1 of 7)

ITEM ENTRY On-line Verification - Check the appropriate boxes as the State Warning Point (Florida Division of Emergency Management) requests that St. Lucie County Department of Public Safety and the Martin County Division of Emergency Management get on the line, prior to initiating the notification. All three agencies must be notified through the SWP or alternate means.

1.

Check appropriate box for drill or actual emergency as the case may be. During exercises, drills, or tests, each message shall be checked THIS IS A DRILL.

2A.

Enter today's date.

2B.

Enter the time (using the official time, normally synchronized with ERDADS) when contact is made with the State Warning Point or the start time of the RM PAR Briefing. For initial notification of classification, this shall be within 15 minutes of the "Emergency Declaration" time in item 5.

2C.

Enter the name of the person making the notification call.

2D.

Enter the message number beginning with #1 and following sequentially in all facilities (e.g., if the Control Room transmitted two messages the TSC would start with #3).

2E.

Check the box for the facility from which the notification is being made.

3.

Site Check the box for the appropriate plant site for the emergency declaration (both St Lucie boxes might need to be checked for dual unit events such as approach of a hurricane).

4.

Emergency Classification Check the box corresponding to current accident classification declared.

5.

Emergency Declaration or Emergency Termination Enter the date and time when the current emergency classification was declared (A) or (B) when the emergency was terminated.

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6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 35 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT ATTACHMENT 1A DIRECTIONS FOR COMPLETING THE FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM (Page 2 of 7)

6.

Reason for Emerqency Declaration Enter the Emergency Action Level (EAL) number (A) (This option is currently not being used at Plant St. Lucie) or (B) enter wording like that found in the EAL information in EPIP-01, Classification Of Emergencies. Wording should be brief yet descriptive enough for the off-site agencies to gain an understanding of the event. It should be clear from the incident description which EAL has necessitated the emergency declaration. Wording should be as non-technical as possible with no acronyms or abbreviations. This information should remain the same throughout update messages, unless there is a classification change.

"*" asterisk and instruction provided at the bottom of form - If Emergency Class escalation is necessary due to rapidly degrading conditions, Then provide the State and County authorities with the initial notification information by transmitting lines 1-6, at a minimum, on the State Notification Form (SNF) and terminate the call by stating that a new notification form will be provided within 15 minutes.

7.

Additional Information or Update Check "None" (A) or (B) Description and enter additional information, if necessary, or reason for update here. For example:

Protective Action Recommendations (PARs) change An occurrence that would otherwise result in a lower emergency classification, on other unit Weather changes affecting public safety Radiation level changes Loss of off-site power, etc.

REVISION NO.:

PROCEDURE TITLE:

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6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 36 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT ATTACHMENT 1A DIRECTIONS FOR COMPLETING THE FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM (Page 3 of 7)

NOTE If the Class A Model (dose projection model) is being used, a 'State Notification Form Summary Sheet' is available which provides information for items 8-11, 13 and 14. The information is in a format similar to that found on the Florida Nuclear Plant Emergency Notification Form.

8.

Weather Data NOTE 10 meter data should be used.

A.

¶10 Wind direction can be obtained from ERDADS by depressing the "EPIP" key, on the top row of the keyboard. The Met Tower Indicator Panel in the Unit 1 Control Room is an alternate source. If these two sources are not available, refer to Attachment 1, Meteorological Data, in EPIP-09, Off-Site Dose Calculations.

B.

If the wind direction is greater than 3600 the wind direction is determined by subtracting 360' from the indicated number. Wind direction should be rounded to the nearest whole number.

C.

Wind direction is always given as "wind from" (an easterly wind, or wind direction 90', means that the wind is blowing from east to west).

D.

When determining the sectors affected, the adjacent sectors on both sides of the actual downwind sector are included. Three sectors will typically be listed.

E.

If the wind is located on the edge of a sector (i.e., 11 0, 330, etc.) an additional (fourth) sector should be added.

F.

Enter the wind direction (wind from) in degrees in item "A."

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6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 37 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT ATTACHMENT 1A DIRECTIONS FOR COMPLETING THE FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM (Page 4 of 7)

B.

(continued)

G.

Enter the downwind sectors in item "B."

Wind Sectors Wind Sectors Wind Sectors From Affected From Affected From Affected 348-11 HJK 123-146 PQR 236-258 CDE 11-33 JKL 146-168 QRA 258-281 DEF 33-56 KLM 168-191 RAB 281-303 EFG 56-78 LMN 191-213 ABC 303-326 FGH 78-101 MNP 213-236 BCD 326-348 GHJ 101-123 NPQ There is no "0" sector There is no "I" sector

9.

Release Status A.

If there are no indications of a release of radioactive material, check box "A" and go to item 11.

A release of radioactive material (during any declared emergency) is defined as:

Any effluent monitor increase of (approximately) 10 times or one decade above pre-transient values OR Health Physics detecting airborne radioactivity levels in excess of 25% derived air concentration (DAC) outside of plant buildings due to failure of equipment associated with the declared emergency.

B.

If a release of radioactive material is occurring, even though it may be less than normal operating limits, check box "B."

C.

If a release has occurred but stopped, check box "C."

Dose Assessment personnel in the TSC or EOF will have this information.

The TSC Chemistry Supervisor, TSC HP Supervisor or EOF HP Manager should be contacted for the data.

0)

REVISION NO.:

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6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 38 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT ATTACHMENT 1A DIRECTIONS FOR COMPLETING THE FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM (Page 5 of 7)

10.

Release Significance Category Do Not Check Any Box in Item 10 if you Checked Box 9 "A" No Release A.

If a release is occurring or has occurred and dose information is not available at the time of notification, check box "A" and follow up as soon as information becomes available.

B.

Check box "B" if both noble gas and iodine release rates are less than or equal to the following:

Noble Gas release < 3.5 E+5 pCi/sec (3.5 E-1 Ci/sec)

Iodine release < 4.6 E+1 pCi/sec (4.6 E-5 Ci/sec)

C.

Check box "C" if either noble gas or iodine release rates exceed the values in "B" (above) but forecasted 1 mile doses are less than either 500 mrem TEDE or 1000 mrem Thyroid CDE. These doses are less than the state's Protective Action Guide (PAG) levels.

D.

Check box "D" if forecasted 1 mile doses are greater than or equal to either 500 mrem TEDE or 1000 mrem Thyroid CDE. These PAG levels require state and county action.

11.

Utility Recommended Protective Actions A.

If there are no Protective Action Recommendations (PARs), check Box "A."

B.

If PARs are necessary, check Box "B". Two formats are provided to record PARs. Use the "sector" format and determine appropriate PARs using the guidance in Attachment 2 to this procedure. Copy the PARs into item 11 "C."

Indicate PARs using only the words NONE, ALL, ALL REMAINING or by listing the letters of the sectors affected. Protective Action Recommendations shall be approved by the Emergency Coordinator (EC) or the Recovery Manager (RM). The "zone" format is for Crystal River Unit 3 use only.

C.

Check the "Yes" box (to consider issuance of potassium iodide (KI) only if:

(1)

A General Emergency has been declared AND (2)

A release of radioactive material is occurring.

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6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 39 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT ATTACHMENT 1A DIRECTIONS FOR COMPLETING THE FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM (Page 6 of 7)

12.

Plant Conditions Answer the three questions "Yes" or "No" by checking the appropriate box.

A.

Is the reactor shut down?

B.

Is the core adequately cooled?

C.

Is the containment intact?

Answer the question regarding the condition of the core as either stable or degrading.

13.

Weather Data NOTE 10 meter data should be used.

A.

¶10 Temperature, wind speed and wind direction can be obtained from ERDADS by depressing the "EPIP" key, on the top row of the keyboard. The Met Tower Indicator Panel in the Unit 1 Control Room is an alternate source. If these two sources are not available, refer to, Meteorological Data, in EPIP-09, Off-site Dose Calculations.

B.

Enter wind speed in Miles Per Hour (MPH) in item "A".

C.

Stability Class - Enter the stability class as determined by using the figure below. The figure shows the relationship between the Delta T displayed by ERDADS and the stability class.

If Delta-T is Then Stability Class is Less than or equal to -1.7 A

-1.6 to -1.5 B

-1.4 C

-1.3 to -0.5 D

-0.4 to +1.4 E

+1.5 to +3.6 F

Greater than +3.6 G

REVISION NO.:

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6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 40 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT ATTACHMENT 1A DIRECTIONS FOR COMPLETING THE FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM (Page 7 of 7)

14.

Additional Release Information This section requires that a release be in progress and completed results of dose assessment be available. Check the "N/A" box if no release is occurring and/or if dose information is not available. Otherwise, provide all information that applies.

A.

Enter the noble gas release rate in curies per second.

B.

Enter the iodine release rate in curies per second.

C.

For an airborne release, enter the date and time started and when terminated, the date and stopped.

D.

For a liquid release, enter the date and time started and when terminated, the date and time stopped.

Projected Dose Information - Enter the projected Thyroid Dose (CDE) in mrem for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (EPIP-09, Manual Dose Calculation Worksheet, Line 5) and the projected Total Dose (TEDE) in mrem for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (EPIP-09, Manual Dose Calculation Worksheet, Line 16) for the site boundary 2, 5 and 10 miles.

15.

Message Received By Enter the name of the State Warning Point Duty Officer or the individual that receives the notification. Enter the time at the State Warning Point (request it from the Duty Officer) and indicate the date the call is completed.

END OF ATTACHMENT 1A

REVISION NO.:

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6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 41 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT ATTACHMENT 2 DETERMINATION OF PROTECTIVE ACTION RECOMMENDATIONS (PARs)

(Page 1 of 5)

NOTE Initial notification from the Control Room may utilize PARs based on plant conditions.

" Once dose assessment begins, PARs should be made utilizing all available data including off-site dose projections, plant conditions and field monitoring data.

" Both plant conditions and off-site doses shall be considered for PARs.

" The most conservative recommendations should be made.

If it is anticipated that a threshold for a PAR will be exceeded, it is neither necessary nor desirable to wait until the threshold is exceeded to make that PAR.

¶12 Conditions (plant information, dose projections and field monitoring results) are to be continually assessed and PARs expanded, as necessary, to ensure that adequate (most conservative) PARs are issued.

112 Previously issued PARs, unless found to be less conservative, are to remain in effect until the threat is fully under control and the event is being de-escalated.

¶12 Only State and County officials can implement, change and/or terminate protective actions.

1.

PAR Flowchart A.

PARs Based on Plant Conditions

1.

Begin in the upper left hand corner of the chart by answering the General Emergency (GE) question.

2.

Correctly answer the questions until you reach one of the boxes that provides PAR information based on plant conditions.

3.

If there is no release, Then go to the PAR Worksheet and fill-in the PARs based on plant conditions. The sectors affected can be determined by referring to number 8, Weather Data, in Attachment 1A, Directions for Completing the Florida Nuclear Plant Emergency Notification Form.

4.

If a release is involved, Then go to Section B, PARs Based on Off-site Dose, below.

Form #PSL-F156 EPIP-08, Off-Site Notifications and Protective Action Recommendations Effective Date 12/10/03

REVISION NO.:

PROCEDURE TITLE:

PAGE:

6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 42 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT ATTACHMENT 2 DETERMINATION OF PROTECTIVE ACTION RECOMMENDATIONS (PARs)

(Page 2 of 5)

1.

(continued)

NOTE

• If the Class A Model printout, State Notification Form Summary Sheet is available, it should be used to compare dose-based PARs against PARs based on plant conditions.

" Calculated off-site doses should be compared to field monitoring data when determining PARs.

B.

PARs Based on Off-site Dose

1.

PARs are based on the Total Effective Dose Equivalent (TEDE or total dose) and / or the Committed Dose Equivalent (CDE, thyroid dose). Do NOT use dose rate values.

2.

If using the Class A Model, Then in Forecast Mode, print the State Notification Form Summary for computer generated PARs.

a.

Go to Section C, PAR Worksheet

3.

If using EPIP-09, Off-site Dose Calculations, Then calculate TEDE and CDE in accordance with the procedure.

a.

Compare the TEDE dose at 1 mile with the values on the Flowchart. Enter the chart at the appropriate dose level by determining if the dose is between 500 and 999 mrem or between 1000 and 4999 mrem or 5000 mrem or greater.

b.

From the selected dose level, move to the right on the chart to the first column, 0-2 miles. The PAR provided corresponds to the calculated TEDE at 1 mile.

c.

Enter the PAR in the 0-2 miles block on the TEDE DOSE table below the PAR Flowchart. The sectors affected can be determined by referring to number 8, Weather Data, in A, Directions for Completing the Florida Nuclear Plant Emergency Notification Form.

d.

Continue to determine the corresponding PAR at 2-5 miles using the calculated 2 mile TEDE, at 5-10 miles using the calculated 5 mile TEDE and the 10 miles plus (To Be Determined (TBD) distance) using the calculated 10 mile TEDE, as necessary.

e.

Enter the PAR information In the appropriate blocks of the TEDE DOSE table.

Form #PSL-F 156 EPIP-08, Off-Site Notifications and ProtocUve AcIjon Rtconwodaltons Effective Date 12/10/03

REVISION NO.:

PROCEDURE TITLE:

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6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 43 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT ATTACHMENT 2 DETERMINATION OF PROTECTIVE ACTION RECOMMENDATIONS (PARs)

(Page 3 of 5)

1.

B.

3.

(continued)

f.

Follow the same methodology for determining the PARs corresponding to the calculated CDE values beginning with the calculated value at 1 mile.

g.

Enter each of the determined PARs in the CDE (Thyroid) DOSE table below the PAR Flowchart.

h.

Go to Section C, PAR Worksheet.

C.

PAR Worksheet

1.

Fill-in the time / date and emergency class.

2.

In Part A, determine the most conservative PARs by comparing the PARs based on plant conditions against those based on off-site dose. It is important to compare PARs at each distance (0-2, 2-5, 5-10) because the basis of the most conservative PAR could be different at different distances.

3.

Enter the most conservative PARs into the table in Part B, Protective Actions Recommended by FPL. Use the word(s) NONE, ALL, ALL REMAINING or list the individual affected sectors by letter.

4.

Obtain review and approval.

5.

Transfer the approved PARs to the Florida Nuclear Plant Emergency Notification Form.

Form #PSL-F 156 EPIP-08, Off-Site Notifications and Protective Action Recommendations Effective Date 12/10/03

REVISION NO.:

PROCEDURE TITLE:

PAGE:

6A OFF-SITE NOTIFICATIONS AND PROTECTIVE PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT ATTACHMENT 2 DETERMINATION OF PROTECTIVE ACTION RECOMMENDATIONS (PARs)

(Page 4 of 5)

Y.

MILE Note MILES NO ACTION EVACUATE SHELTER

1. Sewsrq i=e ored i wc W

-Los of cleciil furidiori req~ired for =*~ prolieclio (e.g., ion of injection with LOCA) OR 0-2 None All None oghco.

p*r.

(oalid CET geater Vin 7Wo F) OR 2-5 None (Sectors Affected) All Remaining CHRRM reading greamtw gon 42 E4 "Air.

5-10 None None All

2. Lin of phy-wrs of Comlr Roourm oW redo op.mlg wrow to ar.

PARs Based on Off-Site Dose (For use with manual dose calculation only. Not to be completed when Class A Model is used)

CDE C,-.- ý. o0 TEDE (Thyroid)

I DOSE DOSEs 1

2-5Miles r

5-10OMiles 1

DOSE DOSEj I Use 1 mile value Use 2 mile valu.

Use 5 mile value TEDE F

CDE 500--999 11000-4999 Shelter A Shelter Shelter mrem re (Sectors Affected)

(Sectors Affected)

'Ds-t0i ow t-is r -,Iuke NO ACTION TEDE 1000-4999 mrem TEDE 5000 mrem or IGreater CDE 5000-24999 Evacuate All mrem Evacuate (Sectors Affected)

Shelter All Remaining Evacuate (Sectors Affected)

Shelter All Remaining COE 25000 mrem or Greater Evacuate

- Evacuate All Evacuate All (Sectors+Affected)

Shelter All Remaining Use the following terms in this table: NONE, ALL, ALL REMAINING or fill in the letters of the sectors affected.

TEDE DOSE Miles NO ACTION EVACUATE SHELTER 0-2 2-5 5-10

>.10 Use the following terms in this table: NONE, ALL, ALL REMAINING CDE (Thyroid) DOSE or fill in the letters of the sectors affected.

Miles NO ACTION EVACUATE SHELTER 0-2 2-5 5-10

> 10 (PEPIEPIP-OMAPP C-RI) ations Effective Date 12/10/03 Form #PSL-F 156 EPIP-08, Oft-Site Notifications and Protective Action Recommend,

REVISION NO.:

PROCEDURE TITLE:

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6A OFF-SITE NOTIFICATIONS AND PROTECTIVE PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT ATTACHMENT 2 DETERMINATION OF PROTECTIVE ACTION RECOMMENDATIONS (PARs)

(Page 5 of 5)

PAR WORKSHEET Time / Date Emergency Class: 0 SAE 0 GE A.

PAR Comparison After comparing the possible recommendations from the PARs flowchart, the most conservative PARs are based on: (check one) 0] PLANT CONDITIONS 0 OFF-SITE DOSE B.

Protective Actions Recommended by FPL:

Use the following terms in this table: NONE, ALL, ALL REMAINING Or fill in the letters of the sectors affected.

NO ACTION SECTORS EVACUATE SECTORS SHELTER SECTORS 0-2 miles 2-5 miles 5-10 miles 10-TBD miles*

• If necessary, add to State Notification Form.

Control Room Signature Emergency Coordinator Technical Support Center Signature TSC EC Assistant / Logkeeper TSC HP Supervisor or TSC Chemistry Supervisor Emergency Operations Facility Signature EOF RM OPS Advisor / Logkeeper EOF HP Manager Form #PSL-F 156 EPIP-08, Off-Site Notifications and Protective Action Recommendations Effective Date 12/10(03 END OF ATTACHMENT 2

REVISION NO.:

PROCEDURE TITLE:

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6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 46 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT ATTACHMENT 3

¶8 NRC REACTOR PLANT EVENT NOTIFICATION WORKSHEET (Page 1 of 2)

NRC FORM 361 U.S. NUCLEAR REGULATORY COMMISSION (12-2000)

REACTOR PLANT OPERATIONS CENTER EVENT NOTIFICATION WORKSHEET EN #

NOTIFICATION TIME FACILITY OR ORGANIZATION IjUNIT I NAME OF CALLER TCILL BACK 0 EVENT TIME & ZONE EVENT DATE IPOWERMODE BEFORE POWERMODE AFTER EVENT CLASSIFICATIONS 1-Hr. Non-Emergency 10 CFR 60.72(b)()

-(v)(A)

Safe S/D Capability AINA GENERAL EMERGENCY GEN/AAEC TS Deviation ADEV (vXB)

RHR Capability AINB SITE AREA EMERGENCY SIT/AAEC 4-Hr. Non-Emergency 10 CFR 60.72(b)(2)

(v)(C)

Control of Red Release AINC ALERT ALE/AAEC W

TS Required S/D ASHU (v)(D)

Accident Mitigation AIND UNUSUAL EVENT UNU/AAEC (iv)(A) ECCS Discharge to RCS ACCS

-xii)

Offite Medical AMED 50.72 NON-EMERGENCY (see next columns)

(iv)(B) RPS Actuation (scram)

ARPS J*xiii Loss CommlAsmt/Resp ACOM PHYSICAL SECURITY (73.71)

DDDD (xi)

Offsite Notification APRE 60-Day Optional 10 CFR 60.73(a)(1)

MATERIAL/EXPOSURE B??.

-Hr. Non-Emergency 10 CFR 60.72(b)(2L J'nvalid Specified System Actuation AINA FITNESS FOR DUTY HFIT (ii)(A)

Degraded Condition ADEG Other Unspecified Requirement (Identify)

OTHER UNSPECIFIED REOMT.

(see last column)

(ii)(B)

Unanalyzed Condition AUNA NONR INFORMATION ONLY NNF (iv)(A) Specified System Actuation AESF NONR DESCRIPTION Include: Systems affected, actuations and their initiating signals, causes, effect of event on plant, actions taken or planned, etc. (Continue on back)

NOTIFICATIONS YES NO WI.L B.E ANYTHING UNUSUAL OR NRC RESIDENT NOT UNDERSTOOD?

YES xplainebove) 0]NO STATE(s)

I DID ALL SYSTEMS LOCAL FUNCTION AS REQUIRED?

0 YES 0 NO (Explain above)

OTHER GOV AGENCIES I I

_I

_IMODE OF OPERATION ESTIMATED ADDITIONAL INFO ON BACK MEDIA/PRESS RELEASE UNTIL CORRECTED:

IRESTART DATE:

10 YES 0 NO Form # PSL-F080 EPIP-08, Off-Site Notifications and Protective Action Recommendations, Effective Date: 08/29/03 and AP 0010721, NRC Required Non-Routine Notifications and Reports

REVISION NO.:

PROCEDURE TITLE:

PAGE:

6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 47 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT ATTACHMENT 3

%8 NRC REACTOR PLANT EVENT NOTIFICATION WORKSHEET (Page 2 of 2)

RADIOLOGICAL RELEASES: CHECK OR FILL IN APPLICABLE ITEMS (specific detalslexplanations should be covered in event description)

ILIQUID RELEASE I IlARFO1 iRFIFASF I IINP ANNn R*PEA,*E I PLA IMur ori Ca=c I Ir*_*,_

I h-ro,,a.J I

U JMONITORED I

UNMONITORED I OFFSITE RELEASE I

T.S. EXCEEDED I

RM ALARMSI AREAS EVACUATED-PERSONNEL EXPOSED OR CONTAMINATED I IOFSITE PROTECTIVE ACTIONS RECOMMENDEDI I*State release path in escription Release Rate (IsecL

% T.S. LIMIT HOO GUIDE Total Activity (CI)

% T.S. LIMIT HOO GUIDE Noble Gas 0.1 Ci/sec 1000 Ci Iodine 10 uCi/sec 0.01 Ci Particulate 1 uCi/sec 1 mCi Liquid (excluding tritium and 10 uCimin dissolved noble gases) 10 u 1__

min 0.1 Ci Liquid (tritlum) 0.2 Ci/min 5 Ci Total Activity PLANT STACK CONDENSERJAIR EJECTOR MAIN STEAM LINE SG BLOWDOWN OTHER RAD MONITOR READINGS ALARM SETPOINTS

% T.S. LIMIT (if applicable)

RCS OR SG TUBE LEAKS: CHECK OR FILL IN APPLICABLE ITEMS: (specific details/explanations should be covered In event description)

LOCATION OF THE LEAK (e.g., SG #, valve, pipe, etc.)

LEAK RATE UNITS: gpm/gpd T.S. LIMITS jSUDDEN OR LONG-TERM DEVELOPMENT LEAK START DATE TIME COOLANT ACTIVITY PRIMARY SECONDARY AND UNITS:

LIST OF SAFETY RELATED EQUIPMENT NOT OPERATIONAL EVENT DESCRIPTION (Continued from front)

Form # PSL-F080 EPIP-08, Off-Site Notifications and Protective Action Recommendations, Effective Date: 08/29/03 and AP 0010721, NRC Required Non-Routine Notifications and Reports END OF ATTACHMENT 3

REVISION NO.:

PROCEDURE TITLE:

PAGE:

6A OFF-SITE NOTIFICATIONS AND PROTECTIVE PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT

¶7 ATTACHMENT 3A DIRECTIONS FOR COMPLETING THE NRC REACTOR PLANT EVENT NOTIFICATION WORKSHEET (Page 1 of 2)

A.

Contact information - to be completed following contact

1.

Name of the person contacting the NRC or other designated FPL contact.

2.

NRC Contacts Name - will be provided upon contact. Also obtain the event number and notification time as received from the HOO should be recorded on the top of the worksheet.

B.

Reactor Plant Event Notification Worksheet, Page 1 NOTE The "EN #" is provided by the NRC.

1.

Notification Time - enter the time contact is made.

2.

Unit - enter the appropriate unit number: Enter "0" for a classification common to both units.

3.

Callers Name - enter the name of the person making the call.

4.

Call back # - enter the number of the ENS phone that you are calling from and the commercial phone number at which you can be reached.

5.

Event time and Zone - enter the military time, the zone will be "EST" for Easter Standard Time or "EDT" for Eastern Daylight-savings Time.

6.

Event Date - enter the date the event is occurring.

7.

Power / Mode Before & Power / Mode After - enter the power in percent and the mode number (1-6) before and after the event.

NOTE Abbreviations / acronyms (e.g., UNU / AAEC, SIT / AAEC, etc.) are for NRC use only.

8.

Event Classifications - check one of the four blocks for General Emergency, Site Area Emergency, Alert, or Notification of Unusual Event.

REVISION NO.:

PROCEDURE TITLE:

PAGE:

6A OFF-SITE NOTIFICATIONS AND PROTECTIVE 49 of 49 PROCEDURE NO.:

ACTION RECOMMENDATIONS EPIP-08 ST. LUCIE PLANT T7 ATTACHMENT 3A DIRECTIONS FOR COMPLETING THE NRC REACTOR PLANT EVENT NOTIFICATION WORKSHEET (Page 2 of 2)

B.

(continued)

NOTE No other blocks in the upper half of the form are required.

9.

Description - provide a written description of the event.

NOTE Check the blocks in the lower portion of the form based on current conditions.

10.

Mode of operation until corrected - provided if known.

11.

Estimate for restart date - enter "unknown".

12.

Additional info on Page 2 - enter yes or no.

C.

Reactor Plant Event Notification Worksheet, Page 2

1.

Fill in as much of the information on the form as is immediately available -

do not create undue delay in making the notification. This information can be gained once the open line of communication is established.

D.

Approval

1.

Information entered on the worksheet shall be reviewed and approved by the EC or RM (if used in the EOF), prior to transmission.

2.

The EC / RM may initial on the worksheet to indicate approval. There is no formal sign-off location on the worksheet.

END OF ATTACHMENT 3A