ML20091N255

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Cycle 18 COLR, Rev 1
ML20091N255
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 08/16/1995
From:
VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML20091N250 List:
References
NUDOCS 9508310089
Download: ML20091N255 (19)
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7 " Vermont: Yankee Nuclear Power Station I

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Cycle'18 l I

-Core Operating Limits. Report;.

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REVISION RECORD.

'.,Q.yqc]1g Revision.) Date' Description

- Initial printing. . Reviewed by.PORC and 14 O '10/89

. approved by management..

15l

0. 9/90 -

Cycle ~15 revisionc. Reviewed by'PORC'an'd approved by management. .

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15- 1 111/91' Incorporate new MCPR limits to allow.

-. operation within the exposure window.

Reviewed.by P.0RC'a.nd approved by management.

16 01 3 32' Cycle 16 revisions. Reviewed by PORC and-i

. approved by management.

4

17. _

.0 ;7/93- Cycle 17~ revisions. Reviewed by PORC and approved.by management.

18 0 .4/95 ' Cycle 18' revisions. Reviewed'by PORC and  !

approved by management.  !

18 ~ 1-. 8/95 Incorporate' new MAPLHGR limits' to account' for -

Less of Stator Cooling Event. Reviewed by 1

! PORC and approved by management.  !

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. ABSTRACT

- This report presents the~ cycle-specific operating limits for.the-

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operation of Cycle 18'of;the: Vermont Yarkee Nuclear Power Station. . The limits are the' maximum ' average planar. linear heat generation rate, maximum if near.

. heat generation rate -:and minimum critical ' power ratio.

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2.0L -. CORE:0PERATINGrLIMITS .

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' 2.11 JMaximum Average: Planar ' Linear He'at -Generation' Rate. Limits . .. .,

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f2.21 ' Minimum Critical' Power Ratio Limits . . . .:. . : . ; .v. . . . . '. ; .

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'2.3: . Maximum ~ Linear Heat Generation Rate Limits .< . . . . . . . . - 3:

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1.0.L INTRODUCTION This report'provides the cycle-specific limits for operation of. the Vermont Yankee Nuclear Power Station in Cycle 18. It includes the limits for  ;

the maximum average planar linear heat generation rate . maximum linear heat

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generation _ rate, and minimum critical power ratio. If any of these limits are-exceed'ed, action will be taken as defined.in the Technical Specifications.

This" report has been prepare'd in accordance with the requirements of_-

- Technical Specification 6'.7.A.4. The core oper'ating' limits have been

- developed using the.NRC-approved methodologies' listed in References 1 through

- 29'and'in-Technical Specification 6.7.A.4 The bases for these limits are in

- References 20, 21,'and 30 through 33. l >

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., V c2.0jCOREOPERATINGLIMITS '

The' Cycle 18 operating limits have been defined using NRC-approved methodologies.- Cycle.18 must be operated within the bounds of these limits l

'and'all others specified in'the Technical Specifications.

2.1 Maximum Averace Planar' Linear Heat Generation Rate Limits j i

During. steady-state power. operation the~ Maximum Average Planar Linear Heat Generation Rat'e (MAPLHGR)'for.each fuel type,.as a. function of_the

average planar exposure, ~shall not exceed the limiting values shown~ in Tables 2.1.1 through-2.1-4. ~For-single recirculation. loop operation, the L11miting values shall be the values from these Tables listed.under the heading

" Single Loop' Operation." These values are obtained by multiplying the values

'for two: loop operation by 0.83. The source of these values is identified on each table. These tables only list' the limits for' fuel- types in Cycle 18.

The MAPLHGR values are usually the most limiting composite of the fuel mechanical design analysis MAPLHGRs and the Loss-of-Coolant. Accident (LOCA)-

MAPLHGRs. The fuel mechanical design _ analysis, using the methods in Reference

- '12.ANmonsUaie's 7' thNal'1 f'uel" ro'ds Yn la? 'a'tYics',

1 op'e'r'a't'ihg ~ a't' th"e b'ound'ing' pwer history, meet the fuel design limits specified in Reference 12. The

- Veraont Yankee LOCA analysis, performed in accordance with 10CFR50, Appendix K, demonstrates that the LOCA analysis MAPLHGR values are bounded at all. exposure points by the mechanical design analysis MAPLHGR values.

i The MAPLHGR actually varies axially, depending upon the specific

, combination of. enriched uranium and gadolinia that comprises a fuel bundle cross section at a particular axial node. Each particular combination of

. enriched uranium-and gadolinia'is called a lattice type. Each lattice type

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has a set of MAPLHGR values that vary with fuel burnup. The process computer.

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- will verify that these lattice MAPLHGR limits are not violated. Tables 2.1-1 l l

through.2.1-4~ provide a limiting composite of MAPLHGR values for each fuel I type, which envelope the lattice MAPLHGR values employed by the process ~

. l computer. When hand. calculations'are required,.these MAPLHGR values are used l for all lattices-in the bundle.

- 2.2 Minimum Critical Power Ratio Limits

' During steady-state power operation, the Minimum Critical Power Ratio

. (MCPR) shall be equal to :or greater than, the limits shown in Table 2.2-1.

The' MCPR limits are also valid during coastdown beyond 10644 mwd /St.

For-single' recirculation loop operation, the MCPR limits at rated flow shall be the values from Table 2.2-1 listed under the heading. " Single Loop l Operation." The single loop values are obtained by adding 0.01 to the two loop operation values. For core flows other than the rated condition, the MCPR limit shall be the appropriate value from Table 2.2-1 multiplied by Kr . l where Kg_ is given in Figure 2.2-1 as a function of the flow control method in use. These limits are only valid for the fuel types in Cycle 18.

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2.3 " Max'imbni' linear Heat' G'en'e' rat:iorf fa'te Limits -

  1. l During steady state power operation, the Linear Heat Generation Rate I (LHGR) of any rod in any fuel bundle at any axial location shall not exceed the maximum allowable LHGR limits in Table 2.3-1. This table only lists the l limits for fuel- types in Cycle 18.

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' _3 i MAPLHGR~Versus Averace Planar Exposure for BP8DWB311-10GZ Fuel-

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~Pla.nti Vermont-Yankee'- . Fue'l' Type: BP80WB311-10GZ MAPLHGR'(kW/ft)- )

. Average Planar ExposureL (mwd /ST). Two-Looo1 Operation Sinole Looo coeration,  !

0.0. 10.93 9.07~

200.00- '11.00 9.13

- ?1,000:00 11.13 9.24

-2,000.00 11.32 9.40

'3,000.00. '

11.52' 9.56

.4,000.00< 11.64 9.66

,  : 5,000.00 11.77 9.77 )

6,000.00' 11.92 9.89 7;000.00 12.11' 10.05 8,000.00_ 12.34 10.24 19,000.00 12.59 10.45 ,

10,000.00 12.83 10.65 l l12,500.00- 13.00- 10.79 15,000.00- 12.81 10.63 20,000.00 12.24 10.16

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~ 35,000.00 10.24 8.50

45,000.00 8.76 7.27 50,735.00- 5.91 4.91 l
Source: Vermont Yankee Cycle 18 Core Performance Analysis Report,

.YAEC-1908, Reference 31; Vermont Yankee Nuclear Power Station' Sinale Looo Operation, NED0-30060, Reference 30; Letter :

h , " Transmittal of Modified Thermal Mechanical MAPLHGR Limits for.

Vermont Yankee Cycle 18 LossLof Stator Cooling Event,"

~

-Reference 33.

. Technical Specification:

References:

3.6.G.la and 3.11.A.

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le ' loo o 4*L'MAPLHGRifor.sinfonbyb8$erationisobtained'by.multiplyingMAPLHGRfor

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'MAPLHGR Versus'Averaae Planar ~ Exposure for BP80WB311-11GZ Fuel! s

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kPlant;: Vermont' Yankee- Fuel) Type:

BP80WB311'-11GZ-  ;

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-.MAPLHGR-(kW/ft) _

  1. iAverage: Planar Expo'sure (mwd /ST) Two Looo Ooeration -Sinole looo Coeration.~

^

'O.00 10.93' s 29.07.

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-200.00- -

11'.00' 9.13:

(1,000,00 9.24

" 11.13

( - - 12,000.00 "

11.32 9.40 -

~ 3,000.00 - ;11.52 ' 9.56l _ ,

4,000;00 11.64 9.66 1

.5,000.00 11.77 9.77 6,000.00- 9.89-( 7,000.00 11.92 10.05 o 12.11'

.8,000.00 12.34 10.24. -

.9,000.00 .12.59- 10.45 1

10,000.00i 10.65

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12.83 12',500.00 13.00 10.79 I

'15,000.00' 12.81' 10.63 20.000.00 12.24 10.16

'25,000.00:

^ 11.'5 5 9:59 ,,

35,000.00- 10.24 8.50 45.000.00 8.76 7.27 50,735.00. -5.91 4.91 l

Source: Vermont' Yankee Cycle 18 Core' Performance Analysis Report, YAEC-1908,; Reference 31: Vermont Yankee Nuclear Power Station Sinale'Looo Ooeration, NED0-30060, Reference 30: Letter.1 "Transaittal of Modified Thermal Mechanical MAPLHGR Limits for

- Vermont Yankee Cycle >18 Loss of-' Stator Cooling Event,"

Reference 33.

' Technical Specification

References:

. 3.6.G.la and 3.11.A.

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L*' MAPLHGR1for single loop operation.is obtained by multiplying MAPLHGR for stwo loop operation by;0.83.

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MAPLHGR Versus Average Planar Exposure for BP80W8335-10GZ Fuel )

. Plant: Vermont Yankee fuel Type: BP80WB335-10GZ-MAPLHGR (kW/ft)

.-Average' Planar Exposure (mwd /ST) Two Looo Operation Sinale Looo Operation.

0.00 11.29 9.37

, 200.00 11.34 9.41 1,000.00 11.48 9.53 2,000.00' 11.69 9.70 3,000.00 11.92 9.89 4,000.00 12.17 10.10 -

5,000.00 12.43 10.32 6,000.00 12.68 10.52 7,000.00 12.87 10.68 8,000.00 13.06 10.84  ;

9,000.00 13.24 10.99 -

10,000.00' 12.99 10.78 l 12,500.00 12.84 10.66 15,000.00 12.65 10.50 20,000.00 11.93 9.90 25,000:00 11.26 - '9.35 35,000.00 9.88 8.20 45,000.00 8.38 6.96 50,593.00 5.65 4.69

_ Source
Vermont Yankee Cycle 18 Core Performance Analysis ReDort, YAEC-1908, Reference 31: Vermont Yankee Nuclear Power Station Sinale Looo Operation, NE00-30060, Reference 30: Letter,

" Transmittal of Modified Thermal Mechanical MAPLHGR Limits for Vermont. Yankee Cycle 18 Loss of Stator Cooling Event "

. Reference 33.

- Technical Specification

References:

3.6.G.la and 3.11.A.

. * ..MAPLHGR for single loop operation is~ obtained by multiplying MAPLHGR for two loop operation by 0.83.

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I k Table 2;1-4 7

MAPLHGR Versus Averaae Planar Exoosure for BP80W8335-11GZ Fuel

Plant: Vermont Yankee fuel Type: BP80WB335 11GZ MAPLHGR (kW/ft)

Average Planar Exposure (mwd /ST)- Two Loop Operation- Single Loop Operation.

0.00 '11.28 9.36.

200.00 11.33 9.40 1,000.00 11.43 9.49 2,000.00: 11.60'.  ; 9.63 -

3,000.00 11.80. 9.79 4,000.00 12.04 9.99-5,000.00 12.30 10.21 6,000.00- 12.53 10.40 7.000.00 12. 73.~ 10.57 8,000.00. 12.94 10.74 9,000.00 13.13 10.90 10,000.00 12.99 10.78-12,500.00 12.84 10.66

15,000.00 12.65 10.50 20,000.00- 11.93 9.90 25,000.00 '

11.26 9.35 35,000.00 9.88 8.20 4

45,000.00- 8.38 6.96 50,593.00 5.65 -4.69 4

Source: Vermont Yankee Cycle 18 Core Performance Analysis Report,

YAEC-1908. Reference 31
Vermont Yankee Nuclear Power Station Sinale Looo Operation, NE00 30060 Reference 30: Letter.

" Transmittal of Modified Thermal Mechanical MAPLHGR Limits for Vermont Yankee Cycle 18 Loss of Stator Cooling Event,"

Reference 33.

Technical' Specification

References:

3.6.G.la and 3.11.A.

~

  • 'HAPLHGR.for single ' loop operation is obtained by multiplying MAPLHGR for

.two loop operation by 0.83.-

5

~7-6

_ 7 -. . . _ _ _ . . ___ _ _ . . , , _ _ _ . , ._ _ _. _ _ _ , _ _ _ ,

.. , , v; e u . . . . . . <

-Table 2.2 g

~

7 h.

=

1 ,

s. g ; o

' . ~

1 nii ,

^+ LMinimum CriticalcPower' Ratio Operatina Limits n

4

. MCPR OperatingLLimits .i

s- '

% t i ..

h~h 1

' Val ue .:of: "N"" .

Single.-

EAverage Control. -Cycle Exposure Two Loop Loop inlRBH; .

JEauation ( A)l j Rod' Scram Time Ranae 0oeratf ort - Operation 2 lj '

"425 ,

IEqual'to orl OiOfto 4000: mwd /St -1.39' 1.40 better:than 4000~to 5500 mwd /St 1.35- 11.36' h -

, .L.C ;0.6 ' . 5500 to 10644 mwd /St 1.33. '1234-  !

, r3.3.C.1.1- 1 H

l Equal ~to or. 0.0 to.4000 mwd /St 1.39 1.40 1 better thani 4000 to 5500 mwd /St~ =1!35 '1.36,  !

. L . C .O .- 5500 to 9035 mwd /St '1.33 1.34'

-3.3.C.1.2 9035 to 10644 mwd /St '1.34 1.35 b 91%; ' Equal to o'r? 0.0 to 4000 mwd /St' 1.39 1.40 I better than 4000 to 5500 mwd /StL 1.35' 1.36 -l L;C.O. 5500 to 6500 mwd /St 1.29- 1.30:

9[

.. - 3 .' 3 . C .1.1 s '6500.to 9035 mwd /St: 1.27 1.28-

- , * ~

9035 to 10644 mwd /St' 1.32 .1.33 EqualLto or- 0.0-to'4000 mwd /St. 1.39 '1.40 s- better than 4000 to'5500 mwd /St 1.35. 1.36

. L.C.0. 15500 to 6500 mwd /Sti l'.29 1.30 1.28

'2 3.3.C.1.2 6500 to-8035 mwd /St 1.27 l 8035 to 9035 mwd /St' 1.30' '1.31 '

9035 to 10644 mwd /St- '1.34 1.35' R f40% ' Equal to or. 0.0~to 4000 mwd /St 19 1.40 e ,, -better than 4000 to 5500 mwd /St 1.' 1.36 L.C.0. '5500 to 6500' mwd /St 1. . 1.30 3.3.C.1.1 '6500 to 8035 mwd /St 1.25 1.26  ;

r .8035 to 9035 mwd /St 1.27 1.28 9035 to 10644 mwd /St 1.32 1.33 Equal to or 0.0 to 4000 mwd /St 1.39 1.40

better than 4000 to 5500 mwd /St- .1.35 1.36 4

L.C.0. 5500 to 6500 mwd /St 1.29 1.30- i 3.3.C.1.2 6500 to 8035 mwd /St- 1 ~. 25 1.26 8035 to 9035 mwd /St 1.30 1.31 1.34 1.35 J 9035 to 10644 mwd /St 1

g -Sources:. Vermont Yankee Cycle 18 Core Performance Analysis Reoort.

YAEC-1908. Reference 31: End-of-Full-Power-Life Sensitivity' Study for the Revised BWR Licensino Methodoloay..YAEC-1822

. Reference 32: and Vermont Yankee Nuclear Power Station Sinole Loog l 00eration.;NE00-30060.. Reference 30. 1 e

^

Te hnical Specification Referencesi 3.6.G.la and 3.11.C.

g ,

<< u 4 1

. i '11 lThe RodLBlock Monitor l(RBM). trip'setpoints are determined by the equation'-

g a. 3i .shown'in Table.3.2.5 of'the Technical-Specifications. ,

12L ;MCPR: Operating LimitsLare increased by: 0,01 for single loop _ operation.

i, - #

8H ,

g

. s

w - - ..

^

! I ~,

3,.p ,..- < ,

.; ,y,-

,.r. r ,

n

/ Table 2 3-l ~

.W ' Maximum'All'Wable o linear' Heat Generat' ion' Rat'e limits V

I- , . .

LMaximum Allowable Linear-

Fuel Tvoe  : Heat Generation ' Rate (kW/ft) 14.4-

~

JBP80WB311 10GZ .

-,3

~BP8bWB311-11GZ-14.4: ,

t BP80WB335-10GZ- ,

14 '. 4 . s

- BP80WB335-11GZ' 14.4 Aq ['_'

=, . -H /So'urce: ?NEDE-24011-P-A. Reference 21..

h;; t8 ,

r

.p, >"

):

k-f d?jp.fichnical-Speciftcation'

References:

- 2.1 A.la, 2.1.B.1, and 3.11.B.

.  : e l'

ly. , ' , - d. '

7 ..e '

d g .

j l

I f

t-i-

+

l l

L 'j .,

e - a +

1

. c e t 7 1 4

_g- 8 p

^ /

a do',- I k' -'

--J( .-

.c .

- Kf-1.4 . . .

EQUATIONS for Kf Ci.rves

Kf 2 1.0

,;  ; f Kf(WT>40%) = A 0.441(WT/100%)

.

  • Kf(WTc40%) =

j,$ .......', .. ..*......*...... Kf(WT> 40 %)*(1.0+0.003 2(40.WT))

, l Where A(102.5%) = 1.3308 A(104.5%) = 1.3406

, , l A(107.0%) = 1.3528 i

'l .

A(!!2.0%) = 1.3793 A(ll7,0%) = 1.4035

. , l l 1.2f- ,

+-

+- +++4-

  • l

, l AUTOMATIC ILOW CONTROL 1.1 .

1

\

. . . . . . . \

l MANUAL ROW CONTROL

  • ~
  • j2_ Scoop Tobe Set Point Calibratica /. . . ... ........

positioned inch that:

Flowmax = 102.5%/

// -

= 104.5%/

= 107.0% . . .

.  ; l l

= 112.05/

= 117.0% - . .

~

0.9 ......... ......... ......... ......... ......... ......... ......... .........

i 20 30 40 50 60 70 80 90 100 Core Flow (%) (WT)

.Fioure 2.2-1 4

f,7 Versus Percent of Rated Core Flow Rate (Technical Specification Reference 3.11.C)

3.0., REFERENCES'

1. Report, A. A. F. Ansari, Methods for-the Anal lysis of Boiling Water 1 Reactors: Steady State Core Flow Distribution Code (FIBWR), YAEC-1234,  !

. December 1980.

2. Report ~,' A. A. F. Ansari and J. T. Cronin, Methods for the' Analysis-of j Bolline Water Reactors: A System Transient Analysis Model (RETRAN), I

.YAEC-1233, April 1981.

3. Report,- A. A. F. Ansari, K. J. Burns and D. K. Beller,' Methods for'the :f Analysis of Boiling Water' Reactors: Transient Critical Power Ratio, j Analysis-(RETRAN-TCPYA01), YAEC-1299P, March 1982. 1

, 4. -Report, A. S. DiGiovine, et al., CASMO-3G Validation, YAEC-1363-A,. April-

~1988. l

^

5. Report, A. S. DiGiovine, J. P. Gorski,'and M. A. Tremblay SIMULATE-3 l Validation and Verification, YAEC-1659-A, September 1988. i
6. Report, R. A. Woehlke, et al.,.MICBURN-3/CASM0-3/ TABLES-3/ SIMULATE-1 Benchmarking of Vermont Yankee Cycles 9 through 13, 7AEC-1683-A, March 1989.
7. Report, J. T. Cronin, Method for Generation of One-Dimensional Kinetics Data-for RETRAN-02, YAEC-1694-A, June 1989.
8. Report V. Chandola, M. P. LeFrancois and J. D. Robichaud, ADolication  !

of One-Dimensional Kinetics to Boilina Water Reactor Transient Analysis

. Methods, YACC-1693-A, Revision 1, November 1989.

9.. Report, RELAP5YA. A ComDuter ProQram for Light-Water Reactor System Thermal Hydraulic Analysis, YAEC-1300P-A, Revision 0, October 1082:

Revision 1. July 1993.

10. Report; Vermont Yankee BWR Loss-of-Coolant Accident Licensino Analysis Method, YAEC-1547P-A, July 1993.

11- Letter from R. s. Capstick ('!YNPC) to USNRC, HUXY ComDuter Code Information fo. che Vermont Yankee BWR LOCA Licensing Analysis Method, FVY 87-63, dated June 4, 1987.

12, LetterLfrom R. W. Capstick (VYNPC) to USNRC, Vermont Yankee LOCA Analysis Method FROSSTEY Fuel Performance Code (FROSSTEY-2), FVY 87-116.

dated December 16, 1987.

13. Letter from'R. W Capstick (VYNPC) to USNRC, Response tc NRC Reouest for-

~- '

Additional Information on the FROSSTEY-2 Fuel Performance Code, BVY 89-65, dated July 14, 1989.

~

7p

1

.c i

-d, -

1

'li :qR *Lette(Lfrom R; W. Capstickl(VYNPC) to USNRC,' Supplemental Information on ,

the FROSST-EY-2 Fuel Performance Code; BVY 89 74, dated August 4. 1989. ' '

1

15. Letter from L.'A. Tremblay, Jr. (VYNPC)-to USNRC, ResDonses to Reauest'
for Additional Information'on FROSSTEY-2= Fuel Performance Code.
8VY 90 045, dated. April 19, 1990.
16. Letthr'fromL.A.lThemblay,=Jr.'(VYNPC)to'USNRC,SuDDiemental Information to VYNPC ADril 19. 1990 Response 1Recardino FROSSTEY-2 Fuel i Performance Code, BVY 90-054 dated May 10, 1990.

l

17. Letter from .L.- A. Tremblay,JJr.. (VYNPC) to USNRC, Responses to Reauest

. for ~ Additional Information on FROSSTEY-2 Fuel Performance Code, BVY 91-024, dated March 6, 1991.

18.- ' Letter from L. A'., Tremblay, Jr. ,(VYNPC) to USNRC, LOCA-Related R'sDonses e

to Open Issues on FROSSTEY-2 Fuel' Performance Code, BVY 92-39, dated March 27,.1992.-

i

'19. Letter from'L. A.LTremblay, Jr.:(VYNPC)'to=USNRC, FROSSTEY 2 Fuel E

Performance Code - Vermont Yankee Response to Remainino Concerns,-

BVY 92-54, dated May; 15, 1992..  !

1

20. 1 Report L.'Schor, et"al.,-Vermont-Yankee loss-of-Coolant Accident Analysis .YAEC-1772. June 1993.

21 '. Report, General Electric Standard ADolication for Reactor Fuel (GESTARTI), NEDE-24011-P-A-10 GE Company Proprietary, February 1991, as amended.

22. Letter, USNRC'to VYNPC, SER, November 27, 1981.
23. Letter. USNRC to VYNPC, SER, NVY.82-157, September 15, 1982.
24. Letter, USNRC to VYNPC.'SER, NVY 85-205,' September 27,'1985.

- 25. Letter, USNRC to VYNPC, SER, November 30, 1977.

~26. Letter, USNRC to VYNPC, SER, NVY 87-136, August 25, 1987.

{

27 - Letter USNRC to VYNPC; SER.-NVY 91-26,. February 27, 1991.

[

. 28. - Letter, USNRC to VYNPC.-SER, NVY 92-192, October 21, 1992.

12 9 . Letter.1USNRC to VYNPC, SER, NVY 92-178. September 24, 1992.

30..

Report.: Vermont Yankee Nuclear Power Station Single Looo Ooeration, J

.NE00-30060. February.1983.

)

-c . ,

4 4 4 --",

^

+

r . . .a-,, - .- , .-. , - . - -

.. - .. , . .. - - .- . . . . - , . . . . . . . . - . ~ . . . . . . - - . .

l: ,

p_ ..

e. ~

' 31," , Report,- M. A. Sironen, Vermont Yankee Cycle 18 Core Performance Analysis a i

Report,{.YAEC-1908, January 1995.

i l- .

-Report ' B. Y. Hubbard, et al.. End-of-Full-Power-life Sensitivity Study

~

- 32i  !

for--the' Revised BWR'licensino Methodology, YAEC-1822, October-1991.. .

L . 33. . Letter; P, J. Savoia to R. T.-Yee " Transmittal of: Modified Thermal.

l Mechanical'HAPLHGR Limits' for;VermontLYankee Cycle 18 Loss of Stator l Cooling Event," PJS 95106, July 25, 1995.

i~

l x

7

-.h

'l p

. I:.

NI t ,

.-k.

13-b

. = i .
v

, , , e , ,

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