L-2002-155, Proposed License Amendment Inoperable Rod Position Indication NRC Requested Referenced Documents for Review

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Proposed License Amendment Inoperable Rod Position Indication NRC Requested Referenced Documents for Review
ML022380333
Person / Time
Site: Turkey Point NextEra Energy icon.png
Issue date: 08/14/2002
From: Mcelwain J
Florida Power & Light Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-2002-155
Download: ML022380333 (25)
v • d • e


Text

AUG 1 4 2002 L-2002-155 F=PL 10 CFR 50.90 10 CFR 50.91 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 RE: Turkey Point Unit 4 Docket No. 50-251 Proposed License Amendment Inoperable Rod Position Indication NRC Requested Referenced Documents for Review Florida Power & Light Company (FPL) submitted the Proposed License Amendment for an Inoperable Rod Position Indication via letter L-2002-152, dated July 29, 2002.

Per telephone conference on July 30, 2002, the Staff requested FPL to provide the attached documents needed to complete their review. Attachment 1 provides the final mark-up of the changes to procedure 0-OP-28.2, Shutdown Margin Calculation.

Attachment 2 provides a training activity plan for Operations personnel regarding the plant conditions affected by the inoperable Rod Position Indication for Shutdown Bank A, rod C-9, and the proposed alternate monitoring method. Attachment 3 provides a discussion of the unit shutdown Mode requirements for RPI repair implementation.

Please contact Walter Parker, Licensing Manager, at (305) 246-6632, ifthere are any questions.

Sincerely, J. P. McLwain Vice President Turkey Point Plant OIH Attachments cc: Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant Mr. W. A. Passetti, Florida Department of Health

/Aoc1 an FPL Group company

1 Turkey Point Unit 4 L-2002-155 Docket No. 50-251 Page 2 Proposed License Amendment Inoperable Rod Position Indication NRC Requested Referenced Documents for Review STATE OF FLORIDA )

) ss.

COUNTY OF MIAMI-DADE )

J. P. McElwain being first duly sworn, deposes and says:

That he is Vice President, Turkey Point Plant, of Florida Power and Light Company, the Licensee herein; That he has executed the foregoing document; that the statements made in this document are true and correct to the best of his knowledge, information and belief, and that he is authorized to execute the document on behalf of said Licensee.

J.I. McEIwain STATE OF FLORIDA COUNTY OF Miami-Dade Sworn to and subscribed before me this Aj4 day of A uc.vr , 2002 by, T. 0. Jones who is personally known to me.

Signature of Notary Public-State of Florida

'ýgy P& OfFFCIAL NOTARY SEAL o( DARIUS D REID

-C . CC800424

-OFIdO" JAN. 3,2003 1 Name of Notary Public (Print, Type, or Stamp)

L-2002-155 Attachment 1 Mark up changes to O-OP-28.2 Shutdown Margin Calculation Procedure

Florida Power & Light Company Turkey Point Nuclear Plant c)

Z-

Title:

Shutdown Margin Calculation Safety Related Procedure Responsible Department: Reactor Engineering Revision Approval Date:

RTSs 94-0031P, 97-1224, 98-1189P, 00-0624, 01-0314 OTSC 0032-99 W97 PS/bclswlbvc

LIST OF EFFECTIVE PAGES Revision Pame Date 2

3 08/08/01 4 08/08/01 5 -0894098!-

6 7 08/08/01 8 .6 81198110 9 08/08/01 10 08/08/01 11 08/08/01 12 --O-9840- -

13 08/0WO.

14 15 08/08/01C 16 08/08/01 W97:JPHIIr/swlbvc

TABLE OF CONTENTS Section Page 1.0 PU RPO SE ..................................................................................................................... 4

2.0 REFERENCES

/RECORDS REQUIRED/COMMITMENT DOCUMENTS ........ 4 3.0 PREREO U ISITES ....................................................................................................... 5 4.0 PRECAUTIONS/LIMITATIONS .............................................................................. 5 5.0 SPECIAL TOOLS/EQUIPMENT .............................................................................. 6 6.0 ACCEPTANCE CRITERIA ....................................................................................... 6 7.0 PROCEDURE 7.1 M odes I and 2 ................................................................................................... . 7 7.2 M odes 3, 4 and 5 ................................................................................................ 7 ATTACHMENTS Attachment I Shutdown Margin Calculation For Modes 1 and 2 ............................................ 8 Attachment 2 Shutdown Margin Calculation for Modes 3, 4 and 5 ......................................... 13 W97 JPHIlr/sw/bvc

1.0 PURPOSE 1.1 This procedure provides administrative and technical guidance for:

1.1.1 Verifying Shutdowih rgm i accordance with Tech Spec 3.1.1.1 for Modes 1, 2, 3 and 4Mrin in a n w 1.1.2 Verifying Shutdown Margin in accordance with Tech Spec 3.1.1.2 for Mode 5, and i 1.1.3 Calculating the amount of Subcriticality in Modes 3, 4 and 5.

2.0 REFERENCES

/RECORDS REOUIRED/COMMITMENT DOCUMENTS 2.1 References 2.1.1 Technical Specifications

1. 3/4.1.1.1
2. 3/4.1.1.2
3. 3/4.1.3.1
4. 3/4.1.3.6
5. 3/4.10.1
6. 1.26 2.1.2 Plant Procedures
1. 0-ADM-554,'Plant Curve Book
2. 3/4-EOP-ES-0.1, Reactor Trip Response'
3. 3/4-EOP-ES-1.1, SI Termination
4. 3/4-ONOP-028.1, RCC Misalignment
5. 3/4-ONOP-028.2, RCC Position Indication Malfunction
6. 3/4-ONOP-028.3, Dropped RCC
7. 3/4-ONOP-046.1, Emergency-Boration ,
8. 0-OSP-040.4, Estimated Critical Conditions
9. 0-OSP-040.16, Initial Criticality after Refueling and Nuclear Design Verification
10. 3/4-OP-046, CVCS-Boron Concentration Control W97"JPHIr/sw/bvc

INSERT A 2.3.1 FPL Calculation No. PTN-4FJF-02-074 Rev 0, "Turkey Point 4 Cycle 20 Shutdown Margin and Minimum Shutdown Boron Concentration Analysis to Support Inoperable Rod Position Indication, PLA # 1,-2002-152," Aug 1, 2002.

2.3.2 Turkey Point Unit 4 "Proposed License Amendment Docket No. 50-251 Inoperable Rod Position Indication," L-2002-152, July 29, 2002.

INSERT B NOTE During Unit 4 Cycle 20 power operation, the position of Rod C-9 in Shutdown Bank A will be determined by an alternate method other than the Analog Rod Position Indication System, until the repair of the indication system for this rod is completed. The alternate method to verify Rod C-9's position is the recorder installed to track parameters of the stationary gripper coil of Rod C-9's Control Rod Drive Mechanism. Rod C-9 is verified to be fully withdrawn when the stationary gripper coil does not change state.

4.4.3 When in Mode 3 or 4 at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by consideration of the following factors:

1. RCS Boron Concentration
2. Control Rod Position
3. RCS Average Temperature
4. Fuel Bumup based on Gross Thermal Energy Generation
5. Xenon Concentration, and
6. Samarium Concentration 4.4.4 The required shutdown margin shall be determined with an increased allowance for the worth of ALL immovable or untrippable control rods.

4.5 Attachment 2 is applicable for typical shutdown conditions, that is, all rods expected to be fully inserted.

4.5.1 IF a Shutdown Margin Calculation/Verification is required for initial startup following refueling, or for Low Power Physics Testing, THEN refer to 0-OSP-040.16, INITIAL CRITICALITY AFTER REFUELING AND NUCLEAR DESIGN VERIFICATION.

4.5.2 IF a Shutdown Margin Calculation/Verification is required for non-initial cycle startup, THEN refer to 0-OSP-040.4, ESTIMATED CRITICAL CONDITIONS.

4.6 IF a Shutdown Margin Calculation/Verification is required for any atypical condition (e.g.,

one or more rods stuck out or stuck partially inserted), THEN consult Reactor Engineering.

Is- - C 5.0 SPECIAL TOOLS/EOUIPMENT 5.1 The Plant Curve Book, and/or other approved analysis for the appropriate unit and cycle.

6.0 ACCEPTANCE CRITERIA 6.1 The Shutdown Margin shall be:

6.1.1 Greater than or equal to the value shown in Tech Spec, Figure 3.1-1 for Modes 1, 2, 3 and 4, and 6.1.2 Greater than or equal to 1% Ak/k for Mode 5.

W97"JPH/r/sw/bvc

INSERT C 4.7 During Unit 4 Cycle 20, the position of Rod C-9 in Shutdown Bank A will be determined by an alternate method other than the Analog Rod Position Indication System, until the repair of the indication system for this rod is completed. The alternate method cannot determine if Rod C-9 is fully inserted following a reactor trip. The alternate method to verify Rod C-9's withdrawn position is the recorder installed to track parameters of the stationary gripper coil of Rod C-9's Control Rod Drive Mechanism. Rod C-9 is verified to be fully withdrawn when its stationary gripper coil has not changed state since the last time it was verified to be fully withdrawn.

4.7.1 When calculating shutdown margin on Unit 4 for Modes 1 and 2, Rod C-9 is assumed to be fully withdrawn if its stationary gripper coil has not changed state.

4.7.2 When calculating shutdown margin on Unit 4 for Modes 3, 4 and 5, Rod C-9 is assumed to be fully withdrawn following a reactor trip.

7.0 PROCEDURE CAUTION With the Shutdown Margin less than that required by Technical Specification 3.1.1.1 I or 3.1.1.2, as applicable, boration at greaterthan or equal to 16 gpm of a solution I containinggreater than or equal to 3.0 wt % (5245 ppm) boron or equivalentshall be immediately initiated and continued until the requiredshutdown margin Is restored. j NOTES

-- - - - - - - - - - - - -TE- - - - - - - - - - -

I" Values determined by precise modeling with neutronics codes are more accurate than I

  • first principles implementation of generic curves. Therefore, documented values
  • supplied by vendor or staff may be substitutedfor calculated values.

, If the actual worth of the inoperable RCCA is NOT known, then the worth of the most 1* reactive rod should be used.

v Obtain as much of the Reference conditions as possible from measurement.

I Design values for this procedure are requiredto be taken from either: I I

I - Plant Curve Book, OR I - Approved analysis I L- - - - - - - - - - - - - - - - - - - - - - -

7.1 Modes 1and 2 7.1.1 IF the unit is in Mode 1 or 2, THEN complete Attachment 1.

7.2 Modes 3, 4 and 5 r - - --- -- -- - - - - - - - - - - - - --

NOTE If the Xenon Worth (Step 4 of Attachment 2) can NOT be easily determined, it may be set

  • Sequalto zero. I 7.2.1 IF the unit is in Mode 3, 4, or 5, THEN complete Attachment 2.

END OF TEXT W97.JPH/nr/sw/bvc

ATTACHMENT 1 (Page 1 of 5)

SHUTDOWN MARGIN CALCULATION FOR MODES 1 AND 2

1. IF one or more Rod Control Cluster Assembly is dropped partially or fully into the core, THEN IMMEDIATELY go to 3/4-ONOP-028.3, DROPPED RCC, and continue with this procedure.
2. IF one or more Ro4 Control Cluster Assembly is misaligned with its associated bank, THEN

_-MMEDIATELYo to 3/4-ONOP-028.1, RCC MISALIGNMENT, and continue with this procedure.

3. Unit ......................................................................................................................
4. D ate ......................................................................................................................
5. T im e .....................................................................................................................
6. Rcord the number of Control Rods that are dropped .........................................
7. Record tl* number'o'" Control Rods that are known to be UNTRIPPABLE .......
8. IF Step 7 is greater than one (1), THEN contact Reactor Engineering and/or Nuclear Fuels for assistance in completing the Shutdown Margin Calculation.
9. Record the following current critical conditions:

9.1 Fractional Reactor Power ........................................................................... iiZ 9.2 Tavg ............................................................................................................ LII °F 9.3 Tref ............................................................................................................. E I°r 9.4 M easured Boron Concentration .................................................................. .. p.m 9.5 Burnup (PCB Section 5, figure 4) 1 MWD/MrU I ~NOTESI l . BOC is defined as 150 MWDIMTU. EOC is the projected cycle bumup and can be I found in the Plant Curve Book (PCB), Section 3, Figure 7, Summary of Reactivity i Requirements and Shutdown Margin.

  • I In Steps 9.6 and 9.7 a linearinterpolationbetween BOC and EOC is appropriate.

9.6 Using the Burnup from Step 9.5 and the PCB, Section 3, Figure 7 (Summary of Reactivity Requirements and Shutdown Margin),

record the "(1) Total Control Bank Requirement".

II F1 Pem 9.7 Using the Burnup from Step 9.5 and the PCB, Section 3, Figure 7 (Summary of Reactivity Requirements and Shutdown Margin),

record the "(2) Less Uncertainty" PCM W97-JPH/1r/sw/bvc

INSERT D NOTE During Unit 4 Cycle 20, Rod C-9 in Shutdown Bank A is verified to be fully withdrawn when its stationary gripper coil has not changed state since the last time it was verified to be fully withdrawn.

INSERT E NOTE During Unit 4 Cycle 20, Rod C-9 in Shutdown Bank A is experiencing a problem with the Analog Rod Position Indication System, which does not affect its ability to trip.

I ATTACHMENT 1 (Page 2 of 5)

SHUTDOWN MARGIN CALCULATION FOR MODES 1 AND 2 r f NOTE In Steps 9.8 through 9.13, it is not necessary to record the RPI for rods greater than or I equal to 228 steps. I L.- - - - - - - - - - - - - - - - - - - - - -

G5 E9 J11 L7 J5 E7 G11 L9 9.8 RPI for CBA F2 B110 Kl4 P6 K2 B6 F14 P10 9.9 RPI forCBB F4 D10 K12 M6 K4 D6 F12 MI0 9.10 RPIforCBC D8 M8 H4 H8 H12 9.11 RPI for CBD G3 C9 J13 N7 B C7 G13 N9 9.12 RPI for SBA E5 Lll L5 Ell H6 H10 F8 K8 9.13 RPI for SBB I NOTEI I Step 10 calculates the worth of inserted rods by comparing each to the worth of CBD. I determination of most deeply inserted.

I Dropped rods ARE NOT consideredin the

10. EXCLUDING DROPPED RODS, calculate the inserted rod worth as follows:

10.1 CBA The most deeply HFP integral rod worth ofCBD Inserted RCCA from at this insertion X CBA conversion factor (PCB Section 3, Figure 7)

Step 9 8 (PCB Section 2, Figure 5) x Ei lilcml 10.2 CBB The most deeply HFP integral rod worth of CBD Inserted RCCA from at this insertion X CBB conversion factor Step 9.9 (PCB Section 2, Figure 5) (PCB Section 3, Figure 7)

W97 JPH/lrtsw/bvc

ATTACHMENT 1 (Page 3 of 5)

SHUTDOWN MARGIN CALCULATION FOR MODES 1 AND 2 10.3 CBC The most deeply HFP integral rod worth of CBD Inserted RCCA from at this insertion X CBC conversion factor Step 9.10 (PCB Section 2, Figure 5) (PCB Section 3, Figure 7)

I pcm]

xLIiI - zzcm 10.4 CBD The most deeply HFP integral rod worth of CBD Inserted RCCA from at this insertion X CBD conversion factor Step 9 11 (PCB Section 2, Figure 5) (PCB Section 3, Figure 7)

I I PM x 10 --I P-l 10.5 SBA The most deeply HFP integral rod worth of CBD Inserted RCCA from at this insertion X SBA conversion factor Step 9 12 (PCB Section 2, Figure 5) (PCB Section 3, Figure 7) xZIiI 10.6 SBB The most deeply HFP integral rod worth of CBD Inserted RCCA from at this insertion X SBB conversion factor Step 9 13 (PCB Section 2, Figure 5) (PCB Section 3, Figure 7)

I P.r] x I I I peu 10.7 Record the total inserted rod worth (the sum of Steps 10.1 through 10.6) I pcm :1 W97 JPH/lr/sw/bvc

ATTACHMENT 1 (Page 4 of 5)

SHUTDOWN MARGIN CALCULATION FOR MODES 1 AND 2

11. Record the worth of those rods known to be UNTRIPPABLE as follows:

11.1 IF Step 7 equals one (1), THEN using the burnup from Step 9.5 and the PCB Section 3, Figure 7 (Summary of Reactivity Requirements and Shutdown Margin), record the interpolated worth of the Most Reactive PAIR of Stuck Rods Worth of most reactive Pair of rods stuck out Most reactive stuck rod worth 1z1J (from notes) o~n, 1i ll = I 11.2 IF Step 7 is greater than one (1), THEN contact Reactor Engineering for untrippable rod worth and record that value here, otherwise N/A this step.

12. Record the rod worth reactivity balance as follows:

Inserted Rod Worth (Step 10.7) 10. I j m Untrippable Rod Worth (Step 11.1, 11.2 or N/A) - * +p Step 6 III X][ 200 pcmod] +]pm

=1F-7 Pcm:

13. Determine the Calculated Shutdown Margin as follows:

Step 9.7 Step 9.1 Step 9.6 I x[ I--Iz I Reactivity Balance (Step 12) - p W97 JPH/Ir/swlbvc

ATTACHMENT 1 (Page 5 of 5)

SHUTDOWN MARGIN CALCULATION FOR MODES 1 AND 2

14. Using the RCS Boron Concentration from Step 9.4, determine the required Shutdown Margin as follows:

14.1 IF Step 9.4 is greater than or equal to 750 ppm, 10 0 0 PM THEN the Required Shutdown Margin is ..................................................

14.2 IF Step 9.4 is less than 750 ppm, THEN the Required Shutdown Margin is:

Step 9.4 pm 1770 - 1.02 X 1 ~ppm Yes No EIEl -

15. Is Step 13 greater than or equal to Step 14.1 or Step 14.2, as applicable?
16. IF Step 15 is NO, THEN THE UNIT DOES NOT HAVE ADEQUATE SHUTDOWN MARGIN. IMMEDIATELY INITIATE AND CONTINUE BO N using 3/4-ONOP-046.1, Emergency Boration, and perform the following:

16.1 Calculate the Required Boron Concentration as follows:

Step 14.1 or 14.2 Step 13 Step 9.4 I f pet I X 0 . 143 PP.m + Sep 16.2 C Pem t B PCM n Ion C

16.2 Calculate the gallons of Acid require'd to increase the RCS Boron Concentration Step 9.4 5245 ppm I PPm I 50,790 gal x In Step 16.1 5245 ppm S PPM 16.3 Add the volume of Acid from Step 16.2 using 3/4-ONOP-046.1, Emergency Boration REMARKS:

Date. Reviewed by:. Date Completed by:.

W97 .IPH/IrL*w/bve W*7 JPHnlrswbvc

ATTACHMENT 2 (Page 1 of 4)

SHUTDOWN MARGIN CALCULATION FOR MODES 3,4 AND 5 Record the following reference conditions:

1.1 Unit ............................................................................................................. . II 1.2 Cycle ........................................................................................................... .. Ll T cne Date 1.3 Shutdow n ........................................................................ I I I I 1.4 Cycle burnup (Plant Curve Book (PCB),

Section 5, Figure 4) MWD;rTU i'e- -. . . . . ..-.-. NOTE . . . . .. - - - 1I 1

The CALCULATION POINT is the point in time post shutdown at which the Shutdown Margin is to be calculated. It is not necessarily the present time.

A... - - - - - - - - - - - - - - - - - - - - - - --

2. Record the following calculation point conditions:

Date Tune 2.1 Calculation Point ............................................................ I 1 Ii 2.2 Time since Shutdown .................................................................................. i]Z Z 2.3 Most Recent RCS Boron Concentration ......................................................

2.4 Average RCS Temperature .......................................................................... I .F 2.5 The Mode: Mode 3: Hot Standby RCS temperature at 350 - 547'F F-]

Mode 4: Hot Shutdown RCS temperature at 200 - 350'F F-Mode 5: Cold Shutdown RCS temperature below 200'F 2.6 Record the number of Control Rods that are NOT fully inserted ................ LI P -- - m- - - - - - - - ~NOTE NOTE- - - - - - - - - - -

e In Step 3 below, Plant Curve Book Section 3, Figure 5A already includes the reactivity effects of the minimum, Hot Full Power, steady state Samarium concentration. Figure 5A conservatively does NOT take credit for the additional build-up of Samarium that occurs after Unit shutdown. m

-i-b- - - - - - - - - - - - - - - -----

3. Using the burnup from Step 1.4, the temperature from Step 2.4, AND the ca co,b6 PCB Section 3, Figure 5A (Minimum Shutdown Boron vs RCS Temperature as a function of Bumup (A""-"I',Xe, record the Minimum Shutdown Boron Concentration ................................................................... PM eec,, .Jr, ,,IrsvvUet,

INSERT F NOTE During Unit 4 Cycle 20, the position of Rod C-9 in Shutdown Bank A will be determined by an alternate method, which cannot determine if Rod C-9 is fully inserted following a reactor trip. Therefore, for the purposes of calculating shutdown margin on Unit 4 for Modes 3, 4 and 5, Rod C-9 is assumed to be fully withdrawn following a reactor trip. The number of rods not fully inserted is determined as follows:

  • IF all rods except Rod C-9 are fully inserted following a reactor trip, THEN the number of rods not fully inserted equals 1.
  • IF another control rod(s) other than Rod C-9 does not fully insert following a reactor trip, THEN Rod C-9 is not counted when determining the number of rods not fully inserted. Rod C-9 is not counted in this case because this rod is specifically accounted for as being fully withdrawn in the reactivity values used to calculate subsequent steps.

INSERT G NOTE During Unit 4 Cycle 20, for the purposes of calculating shutdown margin in Modes 3, 4 and 5, Rod C-9 in Shutdown Bank A is assumed to be fully withdrawn following a reactor trip.

- If all rods except Rod C-9 are fully inserted following a reactor trip, then use PCB Section 3, Figure 5A (Minimum Shutdown Boron vs RCS Temperature as a Function of Bumup (ARI-1, No Xe)).

- If another control rod other than C-9 does not fully insert following a reactor trip, then use PCB Section 3, Figure 5A (Minimum Shutdown Boron vs RCS Temperature as a Function of Burnup (ARI-1-C9, No Xe)).

ATTACHMENT 2 (Page 2 of 4)

SHUTDOWN MARGIN CALCULATION FOR MODES 3,4 AND 5

- NOTE - - - - - - - - - -

ff the Xenon Worth can NOT be easily determined, it may be set equal to zero. m I

mm-- - - - - - - - - - - - - - - - - - - - - -

4. Using the Time Since Shutdown from Step 2.2, AND the PCB, Section 2, Figure 2A (Xenon Worth vs Time After Shutdown), or the ERDADS Poison Program, record the Boron Equivalent of the Xenon Worth as follows:

Xenon Worth pcm + 15.5 pcm/ppm =ppm m

I

. . . . . . OE NOT In Step 5, a linear interpolation for Most Reactive Stuck Rod Worth between BOC and EOC using the Bumup in Step 1.4 is appropriate. j L - - - - - - - - - - - - - - - - m - - - - - - - -

5. 'Calculate the RCCA correction as follows:

5.1 IF Step 2.6 equals zero or one, THEN the RCCA correction equals zero ppm. 0 5.2 IF Step 2.6 is greater than one, THEN using the PCB, Section 3, Figure, Summary of Reactivity Requirements and Shutdown Margini, record the Boron equivalent of those rods not fully inserted as follows:

Most Reactive "C

  • 1- Step 2.6 i] x

- X Si Stuck Rod Worth

+ 7.0 pcm/ppm = pm

6. Record the Corrected Minimum Shutdown Boron Concentration as follows:

I ---Step 3 __Stepm- I- 4 -S -

Step 5.1- or 5.2- - - ---

m NOTE I Step 7 determines whether or not the minimum required SHUTDOWN MARGIN per I I Technical Specifications is being met.

L- - - - - - - - - - - - - - - - - - - - - - -- J

7. Is Step 6 less than or equal to Step 2.3? ....................................................... R YES 0 NO W9Vj *JrPMIIrSWilVc

ATTACHMENT 2 (Page 3 of 4)

SHUTDOWN MARGIN CALCULATION FOR MODES 3,4 AND 5

8. IF Step 7 is NO, THEN IMMEDIATELY perform the following:

8.1 Calculate the gallons of Acid required to increase the RCS Boron Concentration to greater than or equal to that of Step 5 as follows:

50,790 gal x In (5245 ppm - 6m =

mgal Step[6(25 I (5245 ppm -

8.2 Add the volume of Acid from Step 8.1, using 3/4-ONOP-046.1, EMERGENCY BORATION.

9. IF Step 7 is YES, THEN record the Excess SHUTDOWN MARGIN as follows:

Step 2.3 Step 6 I ppm - ppm X 7.0 pcm/ppm =

CAUTION Steps 10 and 11 are not Tech Spec related. They provide additionalinformation for determining the subcriticalityby taking creditfor ALL fully inserted control rods.

I NOTE I In Step 10, a linearinterpolation for Most Reactive Stuck Rod Worth between BOC and I EOC using the Bumup in Step 1.4 is appropriate. j

10. Calculate the RCCA correction as follows:

10.1 IF Step 2.6 equals zero, THEN using the PCB, Section 3, Figure 7, "Summary of Reactivity Requirements and Shutdown Margin", record the Boron equivalent of the Most Reactive Stuck Rod as follows:

Most Reactive Stuck Rod Worth I Pcmr + 15.5 pcm/ppm =

I :ppm W97 JPH/lrlsw/bvc

2 ATTACHMENT ATTACHMENT 2 (Page 4 of 4)

SHUTDOWN MARGIN CALCULATION FOR MODES 3,4 AND 5 7, "Summary of 10.2 IF Step 2.6 is greater than one, THEN using the PCB, Section 3, Figure of those Reactivity Requirements and Shutdown Margin", record the Boron equivalent rods not fully inserted as follows:

Most Reactive Step 2.6 Stuck Rod Worth

[1- L] X [pcm + 15.5 pcm/ppm [PPM

11. Determine subcriticality as follows:

11.1 Result in ppm:

Step 3 Step 4 Step 10.1 or 10.2 ppm PPM ppm 11.2 Result in pcm:

Step 11.1 X 7.0 pcm/ppm= L pcm Completed by. Date: Reviewed by: jDate:

FINAL PAGE W97'JPH/IrlswlbvC

L-2002-155 Attachment 2 Operation's Training Activities Plan for Technical Specification proposed changes related to Inoperable Rod Position Indication for Shutdown Bank A, Rod C-9 Prior to implementation, Turkey Point will ensure the following items have been completed:

1. Issue a Night Order to all Operation's personnel informing them of the changes.
2. Issue a Training Brief to Operations personnel detailing the changes. The Training Brief will be presented by a member of Operation's management to each Operating crew's Licensed personnel upon their return to shift.
3. Issue a Problem Status Summary to give guidance on operation of the installed recorder connected to monitor rod C-9 stationary gripper coil.
4. Issue a Special Instruction, detailing the specific procedures that were affected.
5. Training on the installed alternate instrumentation will be scheduled into the Licensed Operator Continuing Training Program.

4,,

L-2002-155 Attachment 3 ShutdoWn Mode Required for RPi Repair In response to NRC questions regarding repair of the Unit 4 Analog Rod Position Indication (RPI) for Shutdown Bank A, rod C-9, at the earliest Mode 3 outage versus the earliest Mode 5 outage, the following description of plant maneuvers, surveillance requirements and challenges to plant systems is provided.

To repair the Unit 4 Analog Rod Position Indication (RPI) for Shutdown Bank A, rod C-9 requires the plant to be in cold shutdown Mode 5. Should Unit 4 experience a plant condition that requires shutdown to Mode 5 prior to the next scheduled Unit 4 refueling outage in October 2003, such a shutdown should be of sufficient duration to effect repairs to the RPI for rod C-9.

In the event of an unplanned shutdown requiring shutdown of Unit 4 to only Mode 3, the plant maneuvers required to then proceed to cold shutdown (Mode 5), solely for the purpose of making repairs to the C-9 RPI, with a subsequent plant startup from cold shutdown, would impose unnecessary thermal cycles and shutdown/startup related challenges to primary and secondary plant systems.

The standard Turkey Point forced outage schedule duration for a "hot" Short Notice Outage (SNO) is 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br />, while the standard for a "cold "SNO is 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br />. The significant differences are summarized below.

Plant Maneuvers:

RCS cool-down from 547 to 350 degrees in order to place RHR in-service RCS cool-down on RHR to <200 degrees (Mode 5)

Collapse the pressurizer bubble and cool-down the pressurizer - solid plant operations Surveillance Requirements:

OSP-206.1 Cold Shutdown IST Valve Exercising OSP-74.5 FW Reg. Valve IST Valve Exercising OSP-41.17 RCS Boundary Valve Leakage Testing OSP-41.18 RCS Boundary Valve Leakage Testing OSP-41.19 RCS Boundary Valve Leakage Testing OSP-41.4 OMS Testing OSP-50.2 RHR Pump IST During CSD OSP-53.4 Containment Integrity (Inside Containment)

OSP-205 Locked Valve List (Inside Containment)

OSP-72 MSIV Valve Exercising OSP-41.23 Pressurizer Heater Output Check (Required For Solid Operations)

L-2002-155 Page 2 Challenges to Plant Systems:

Thermal cycling of all Primary and Secondary Systems Operation of cold shutdown cooling systems with solid plant operations- PORV challenge Unnecessary Surveillance Testing, Valve Cycling and System/Component Alignments

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