ML20054H641

4 to Core Performance Parameter Check, Periodic Test

ML20054H641
Person / Time
Site:	Brunswick
Issue date:	06/02/1982
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20054H623	List: ML20054H622 ML20054H638 ML20054H641 ML20054H644
References
PT-1.11, NUDOCS 8206240288
Download: ML20054H641 (7)

Text

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(Doc.) Date DIN No.

Time File No. 07-13321.1 Unit No. Q+ RET +CDtq-LIFE

, Reference (TT #) _

System (s)

Toreman/ Supervisor Revision No.

Component ids

, CAROLINA PORER & LIC11T COMPANY BRUNSWICK STEAM ELECTR C Pl.AN'r UNITS 1 and 2 s

PERIODIC TEST: PT1.'.!!

, l CORE PERFOR!!ANCE PARAMETER CIIECK l kQUENCY:"A. Onec/24 hours"during steady state c;.r: N- s E25% power. . *.

Each time the reactor power level has$been

*B. -

increased by at least 15% of rated' thermal

• power and steady I st' ate operating conditions -

have been established. -

C. In,itially and every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when in a limiting

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. control rod pattern. .

Revision No.

• Approved: _ ((J///f/ dd & '

^

14 ,,

Date: 8

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1. 131vose .. . .

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The purpose of this PT is to prescribe the procedure for obtaining the basic core performance parameters required by Technical Specifications 4.2.1, 4.2.2, 4.2.3 and 4.2.4, and to calibrate ,the APRM channels to c- 3 ,

read f_ actual core thermal power as required by Technical Specification L

, Table 4.3.1-1, Item 2.f.

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i II. Acccotance Criteria .

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This PT is acceptabic when it is shown by the certifying signature that {

the parameters have been obtained correctly according to this instruction, i that at least two operable APRM's per trip system are reading f_ actual

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• If this PT has been previously done for that 24-hour period, then the 8 t

infomation on Page 2 of this procedure can be documented in the Shif t -

Foreman's Log in lieu of filling out data forms of PT 1.11; however, +

all acceptance criteria shall be applied. , ,

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8206240288 820621  !.

PDR ADOCK 05000324

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2 cf 6 II. Acceptanec Crfterfa_(Cont'd) core power no calculated by heat balance (OD-3), and that all of the . .

situationc belou exist: . . .

CMPF** <2.60 (Unit No. 2 7x7 fuel) MFLCPR <1.0 32.43(8x8 fuel) MAPitAT 51.0

<2 39 (8x8R fuel) .~MLHGR <13.4Kw/ft for 8x8 and 8x8R fuel

.<~ Limits shown in' Table

- 1.11-1 for 7x7 fuel.

III. Precautionn .

A. Special carc shou 1d be taken in recording data. Errors on the nonconocrvative side coulp cause operation that night lead to a viointion of Technical Specifications. -

B. If the value of any of'the core performance par ce,ters are found to cxeced their limits, itnediately notify the Shift Forecan. .

C. During APPJI gain adjunt= cats,'the plant should be held at a steady -

state operating condition. ,

IV. Eculpecnt List .

J A. 4010 Process Computer B. Slide rule or cicctronic calculator ,

> V. ' Annunciations Expected .

Nonc ,

VI. Initial Conditiond_ , ,

A. Power > 25%. ..

B. Verify .againct the Control Roon Operating Manual Index that the latcot revision of this PT is being used.

VII. Procedure ..

1. If the process computer in availabic, attach copics of P1, OD-6 Optiono 3 and 4, and OD-3 Option 2. The OD-3 Option 2 should be 7 taken after all APFJi gcin adjustments are cocplete. CD-10 Option j 1 should nico be attached if possibic. ,

I 1 2. If the process computer is unavailable, attach calculations... ...

. **If the respective peaking factor limits are execeded at power icvels other than 100%, the APRM readings chall be adjusted upward by the factor:

'CMPF for,7x7 fuel, _C MPF for 8x8 fuel, and CMPF for 8x8R fuel.- m-

. 2.60 2.43 - 2.39 g

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<> BSEP/Vol. X'/PT 1.11 -

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. 3 cf 6 VII. Procedure (Cont'd)

3. Sum:sarize data in respective blanks below: .

a. 1. CMWT (%) 5. MLEGR

2. WT (%) 6. MLHGR LIMIT

3. CMPF . 7.. MAPPAT

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4. P2 AVG. EXP.*** 8. MFLCPR

b. ferify the APRM GAF's for at least two operable APRM's in each trip system are <1.00. Also verify that they are set properly for the above peaking factor. (See Note ** on Page 2.) ,

A' ' C E B .. D -

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4. Verify that the acceptance criteria listed in Section II. representing the appropriate Technical Specifications limits are met. ,

. 5. Record the follo' wing data belo'w:*** . . -

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' (a) Condenser Vacuu: A B 3 , T000 T001 LOOO

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(Barometric Pressure) .

(b) , Main Steam Pressure -

at Turbine T017 (c) Tur>ine control valve positions-3 (from turbine gauge board indicators)

CV-1 CV-2 CV-3 CV-4

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• • • bptional data (not required for PT acceptability). .

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i BSEP Vol. X/PT 1.11 Rev. 14

. 4 cf 6 VIII. _CE! ERAI, C0!NE!;TS/PEC0!CT.? DATIO?:S

• CorrectiveActionReg'udred: a. ( ) None

b. ( ) Troubic Ticket No.

Shift Foreman c. ( ) Other (explain)

Initials PT perforced by: _

Initials Name (print) -

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PT has been satisfactorily completed / -

Nuc1 car Eng./ Project Engineer Date

' PT has NOT been satisfactorily completed and . ~

PT Exception Form is Attached

/ Date .

Nuc1, car Eng./ Project Engineer

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Reviewed by: Date:

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Rev.14 O

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. - 5 ef 6 Procedure for PT 1.11 Using Process Computer Performance of PT 1.11 with the process computer is done above 25% power to comply with the Technical Specifications relating to core thermal limits. If the value of any core performance paramet.cr is determined to ' exceed the Technical Specification limits, i= mediately notify the Shift Forc=an and the Shif t Nuclear Engineer who will be responsible for reestablishing operation within limits.

The procedure is to obtain a periodic log P1 by demanding OD-20 from the operator's console. .Upon'. completion of the program (%10 to 15 min.), demand OD-6 Options 3 and 4, as well as OD-3 Option 2. These edits will be attached to PT 1.11. Also, an OD-10 Option 1 will be attached.

The percent pouer is obtained by divid'ing the CMWT (Core Megawatt Thermal).

from the P1 by 2436 and multiplying b'y'100. This number should not ' exceed

• 100%. -

The percent core flow is obtained by dividing HT (core flow total) from the P1 by 77 and multiplying by 100. -

The Core Maximum Peaking Factor (CMPF) is obtained from the P1 and should not '

exceed 2.45 at 100% power for 8x8 fuel, 2.48 for 8x8R fuel, and 2.60 for Unit No. 2 7x7 fuel. If the respective peaking factor limits are exceeded at power levels other than 100%, the APRM readings shall be adjusted upward by the factor _C:TF, CMPF or CMPF' for limiting 8x8, 8x8R or 7x7 fuel type, yespectively.

s 2.43 2.39 2.60 -*

• The Maximum Lfnca'r" Heat Generation Rate (MLHGR) is obtained by multiplying the core maximum fraction of limiting power density (CMFLPD) from P1 by 13.4 Kv/ft for Unit No.1, or 18.5 Kw/f t for Unit No. 2 if the CMFLPD occurs in a 7x7 fuel assembly, or 13.4 Kw/ft if the CMFLPD occurs in an 8x8 fuel assembly.

The Maximum Average Planar Linear Heat Generation Rate Ratio (MAPRAT) is obtained from OD-6 Option 4. This ratio should be less than or equal to 1.

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The Mini =um Critical Power Ratio (MCPR) is obtained from OD-6 Option 3. Both units scoop tube ecchanical' stops are set at <102.5%. Verify Recire. pu=p controllers are in manual for using the 102.5% curve. If in master Auto, use the " Auto Flow Control" Line. The maximum fraction of limiting CPR (MFLCPR) is obtained by dividing CPR Limit by the MCPR. MFLCPR should be less than or equal to 1.

ge 8g . . . . . , w.

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BSEP Vol. X/PT 1.11

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6 of 6 l

l Tabic 1.11-1 ML11GR Limits as a Function of Node Number bcini Component ML11GR Limit (7 x 7) Iw/f t of Mode .

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24 18.02 23-

• 18.04 .

22 18.06 2Y i Y8:08

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20 18.10., ,

- .,,1, 9 _ _ ,

18.12 _ __

18 18.14 17 18.16 16 18.18 .

15 18.20 .

14 -- -

18.22 <

I

13- 18.24 l

32 .=

-1_8.26- ,,,

.,) 1 18.28*

10 . 18 30

. 9 ~8.32 1

8 18.34 .

7 18.36 r .

> 6_ 18.38 5 35 18.40 l 4 18.42 __

? 3 18.44 e

= 2 18.46 1 1 __

18.48 -

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I llSEP Vol. X/PT 1.11 Rev. 14 J

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