ML20148H242

Submits Proposed Change 145,Suppl 4,to Tech Specs,Modifying Tech Specs 3/4.2 & Associated Bases to Reflect Escalation from Zero to Max Allowable Power

ML20148H242
Person / Time
Site:	Yankee Rowe
Issue date:	07/15/1977
From:	Vandenburgh D YANKEE ATOMIC ELECTRIC CO.
To:	Office of Nuclear Reactor Regulation
References
WYR-77-68, NUDOCS 8011170708
Download: ML20148H242 (7)

Text

. Proposesfl%ange ~pJ 1

. . / mitment No. 4  ;

Tslaphone 617 366-9011 7to-390-0739 1

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YANKEE ATOMIC ELECTRIC COMPANY

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gt, , 20 Turnpoke Road Westborough, Massochusetts 01581 )

• M p)rb E5 Ulat0Ty D0cket File July 15,19H ,

United States Nuclear Regulatory Commission OT]

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Attention: Of fice of Nuclear Reactor Regulation /, , 'O References (1) License No. 7PR-3 (Docket No. 50-29)

(2) Proposed Change No. 145, Supplement No. 1, April 13, 1977.

Subject:

Changes to the Core X111 Performance Analysis Pursuant to Section 50.59 of the Commission's Rules and Regulations, Yankee Atomic Electric Company hereby proposes the following modification to Appendix A of the Operating License.

PROPOSED CHANGE: Reference is made to the Technical Specifications of Licente No. DPR-3 and Attachment B, " Yankee Nuclear Power Station Core XIll Perf ormance Analysis", of Reference (2) above. It is proposed that:

(1) Specification 3/4.2 (attached) and its associated bases be modified to reficct power escalation f rom zero te maximum allowable power; .

(2) The attached Table 5.1-2 replace the corresponding page in Reference (2), and; (3) The attached Section 8.0 replace the corresponding Section in Reference (2).

t REASON FOR CRANCE: The change to the Technical Specifications allows power escalation from zero power to maximum allowable power without an intermediate  :

hold. A hold may be necessary in some c. ses during power operation to reduce xenon peaking; however, it is not required when xenon is allowed to decay ,

for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or more.

The change to Table 5.1-2 of the Core X111 Core Performance Analysis  ;

is the iticlusion of the Technical Specification value of shutdown margin.

The change to Section 8.0 of the Core XIII Core Performance Analysis reflects'the addition of two more critical boron measurements, the  !

80111g E THIS DOCUI,1ENT CD:frAIN37 P00R QUhllTY PAGEL _ , -

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U.S. Nuclear Regulatory Commission July 15, 197' Att: Office of hiclear Reactor Regulation Page 2 measurement of control rod Group B, a power distribution map at approximately zero power, a measurement of power coefficient and a report on the startup physics testing.

SAFETY LONSIDERATIONS: The above changes do not alter the Core Performance Analysis described in Reference (2). Therefore, it remains our conclusion that Core X111 operation within tbc proposed specifications will not endanger the health and safety of the public.

This proposed change has been reviewed by the Nuclear Safety Audit and Review Committee.

SCHEDULE OF CHANGE: The Core XII-XIII ref ueling schedule began June 10, 1977. We respectfully request review of this Proposed Change by the Coemission as soon as practical.

Any further questions regarding this supplement should be directed to Mr. Richard J. Cacciapouti at our Engiraering Office, 20 Turnpike Road, Westborough, Massachusetts, 01581, (617 ) ? s6 'Ju ? 1. , Extension 2807.

Very truly youra, YANKEE ATOMIC ELECTRIC COMPANY MDb D. E. Vandenburgh Senior Vice President COMMONWEALTH OF MASSACHUS ETTS

378.

COUNTY OF WORCESTER )

Then personally appeared befo re me, D. E. Vandenburgh, who being duly sworn, did state that he is Senior Vice President of Yankee Atomic Electric Company and that he is duly authorized to execute and file the foregoing request in the name and on the behalf of Yankee Atomic Electric Company, and that the statements therein are true to the best of his kr.owledge and belief .

I IM h O 'R Armand R. Soucy Notary Public My Commission Expires September 9,1977 l

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y 1 POWER DISTRIBUT10tl LIMITS _

SURVEILLA!;CE REQ'JIREMEllTS (Continued) __

4.2.1.2 The bric.i f:ctcrs shall be included in the calculation of peak full power LHGR:

a. Heat flux power peaking factor, F , neasured using incore instrumentetion at a power >105.

b. Effect of inserting the control croup from its position at the time of measurement to its insertion limit, F; cs shown in Figure 3.2-2. The rod insertion limit is shown in Figure 3.1-1.

c. The multiplier for xenon redistribution as a function of core lifetime I

as given in Figure 3.2-3. In accition, if control rod Group C is inserted below 75 inches, allowable power may not be regained until power has been at a reduced level aefir.ec below for at least twenty four hours with I

control rod Group C between 75 and 90 inches.

Rcduced power = alicwaole fraction of full power times multiplier given 1; Figure 3.2-4.

Exception: 1. If the rods are inserted below 75 inches and power does not go below the reco;eo power calculated above, holo at the iowest attained po,ter level for at least twenty fcur hours with control rc" Group C between 75 and 90 inches j

. before returning to alowa51e power.

2. If the rods are inserted below 75 inches and zero power l is held for more tnan 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, no reduced power level l need be teld on the way to the allowable fraction of full power.

d. Shortened stack height f cd.or,1.009.

c. Measurement uncertainty, 1.05.

f. Power level uncertainty,1.03.

g. Heat flux engineering f actor, Fh,1.04.

h. Core average 14 near heat generation rate at full power, 4.40 kw/f t. l ,

4 . 2.1. 3 At least onct per 1000 EFFH, the following limits shall be determined by calculation not to be exceeded at RATED THER.!AL POER:

a. Hottest channel exit coolar.t tc porature 1602 0F, and I 0  !

b. Maximum clad surf ace tezerature in hottest chcnnel 1637 F. i v.u;ver m-T _

3/4 2-2

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3/4.2 P0iiED DISTRIBUTICN LIMITS I

BASES 6

The specifications of this section provice assurance of fuel integrity curing i Condition I (Ucrnci Operation) and II (Incidents of Mocerate Frequency) events _by:  !

(a) mairaair.ing tha .tiair.. a GT. in the core >l.30 during normal operation ar.d in  :

short tem transiencs; and (b) limiting the fTssion gas release, fuel pellet-  ;

temperature and clacair.g cacnanical properties to within assumed design criteria. l 3/4.2.1 PE!? LINEla EIAT CE:'IP ATION P *TE a l

.. Limiting the peak linear heat generation rate (LHGR) during Condition I events pro / ides assurance that the initial conditions assumed for the LOCA analyses  ;

are met and the ECCS acceptance criteria limit of 2200 F is not exceeded. ,

1&en operat ing at constant power, all rods out, with equilibrium xenon, i power peaking in the Yankee Rowe core cecreases monotonically as a function of cycle '

burnup. This has been verified by both calculation and measurement on-Yankee cores _

and is in accord with the expected behavoir in a core that does not contain burnacle poison. The all-rods-out power peaking measured prior to exceeding 75% of RATED  :

THERMAL P0ilER af ter each fuel loading thus provides an upper cound on all-rods-cut  !

power peaking for the remainoer of tnat cycle. Thereafter the measured power peaking '

shall be checked every 1000 equivalent full power hours ano tne latest measurec '

value shall be usec in the computation. The only eTrects which can increase peaking beyond this value would be control rod insertion and xenon transients and these -

are accountec for in calculationg peak LtiGR.

The core is stable with respect to xenon, and any xenon transients which may be excited are rapidly damped. -

3 The xenon multiplier in Figure 3.2-3 was selected to conservatively account .

for transients wh'ch can result from control red motion at full power.

The limits on power level and control rod position following control rod insertion were selected to prevent exceecing the maximum allowable linear heat generation rate limits in Figure 3.2-1 within the first few hours following return to power af ter the insertion. !!ith Yankee's highly duped core, the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> hold allows sufficient time for the initial xenon maldistribution to accommodate itself to the new power distribution. The restriction on control rod location during these 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> assures that the return to allowable fraction of full power will not cause additional redistricution due to rod motion.

After 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> at zero power, the averace xenon concentration has decayed to about:20% of the full power concentration. Since the xenon concentrations are  !

' so low, an increase in power directly to maximum allowable powe' creates transient peaking well below the valde imposed by the xenon redistributio,1 multiplier. Tnus, any increase in power peaking cue to this operation is below the value accounted  ;

for.in the calculation of LHGR. I YAD:EE-ROWE B 3/4 2-1

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i Tabic 5.1--2 SHUTD0'a"4 REOUIREME!.TF . % ao 1

i Core XIII Core XI BOL EOL BOL EOL 10.52 10.64 10.71 10.89 Total Control Rod Worth 2.62 2.76 2.79 2.90 Worth of Stuck Rod 7.90 7.88 7.92 7.99 Total Worth Less Stuck Rod Total Worth Less 7.5% Uncertcinty 7.31 7.29 7.33 7.39 l Allowances Fuel Tc=perature Variation .55 .85 1.75 2.04 Moderator Tecperature Variation .24 .52 0.21 0.46

.03 .06 0.03 0.06 Moderator Volds Operational Maneuvering Band .11 .18 0.80 0.80 Shutdon Margin 4.72 4.72* 1.00 1.00 5.95 6.33 3.79 4.36 Total Allowances Excess Shutdown Margin (for shutdown 1.36 0.96 3.54 3.03 f rom HFP to IIZP) l l

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• Qanged to a;;ree with the Technicc1 Specifiestion.

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8.0 STARTUP PROGRAM 4

Following ' refueling 'and prior to vessel reassembly, fuel assembly position will

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be veri fieo by. or car .a ter television. '

! Yar.kee-Roue Core XIII Startup Program will include the following tests:

1. Control rod operacility test will be perfon11ed by moving each rod group in turn from 0" to 90" to 0" and verifying control rod momvement by the rod.

position indic: tors. . l

. 1 I 2.. Control rod drop time measurement will be conducted by withdrawing one rod group at a time to 90 inches, dropping it and measuring its drop time with l

,a recording oscillograph. 1

3. Just critical boron concentration is determined by placing the reactor just critical, allowing for system equilibrium, taking a series of main coolant boron samples. This will. be done as close as possible to the conditions of i  !

all rods out, Group C inserted and Groups A and C inserted. I I

4. Rod group worths of Group C, Group A and Group B will be detennined. This is done by establishing a boron change, balancing the reactivity change with  !

a control roo position change ano measuring the worth of the roa steps witn i a reactivity computer.

5. Measurement of the ejected control rod worth is aone by balancing a small boron concentration change witn movement of tne single rod and measuring the reactivity change with the reactivity ccmputer. The most worthy ejected rod

. will be measured. In adoition, the second most worthy ejected rod may be measured by a rod-swap or bcron change method. -

6. Measurement ei the dropped control rod worth is completed by balancing a small boron concentration change with rod movement and measuring the reactivity change with the reactivity computer. The most worthy dropped rod will be measured.

In addition, the secono most worthy dropped rod may be measured by a rod swap or boron change riethod. ,

7. Moderator temperature coefficient measurement is ccmpleted by changing main coolant temperature and measuring the reactivity change with the reactivity computer. Several such measurements are completed for each of a number of equilibrium boron conditions.

8. Power and Xenon defects are measured using a reactivity balance before and after power ascension. The two defects are not separated.

9. Power distributions will be measured at approximately zero power and as soon  !

as the reactor is at steady state power (5001 Power Level 175%). This is cone with the incore instrumentation.

10. Power ccef ficient will be measurea at a power level approxirately 10', oelow l maximum alle. able power. This will be cone by cbserving the change in baron  !

- frem one.p.ar level to an tner ard uking appropriate corrections for control rods, moderator temperature, xenon and samarium. l 1

11.. A startup test report on the above will be submitted t NRC in the required i period of time. I 1

l } U.c. NUCLE AR REGULATORY CoMMlf N l OOCKET NUM ER NRL PORu 195 (2 76) , . . .

.2 NRC DISTRIBUTION ron PART 50 DOCKET MATERIAL TO: FROM: DATE OP DOCUMENT Yankee Atomic Elec Co NRC 7-15-77 Westborough, Mass 01581 ATE RECEIVED D.E. Vandenburgh 7 20-77 N

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