ML20002A486

Amend 44 to License DPR-3,revising Tech Specs Re ECCS Accumulator Actuation Time Delay Setting & Burnup Dependent Linear Heat Generation Rates

ML20002A486
Person / Time
Site:	Yankee Rowe
Issue date:	11/29/1977
From:	Schwencer A Office of Nuclear Reactor Regulation
To:
Shared Package
ML20002A485	List: ML20002A484 ML20002A486 ML20002A487 ML20002A489
References
NUDOCS 8011170347
Download: ML20002A486 (11)

Text

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UNITED STATES u.g.

g NUCLEAR REGULATORY COMMisslON

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WASHINGTON, D. C. 20555

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DOCKET NO. 50-29

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-YANKEE ~ NUCLEAR POWER STATION (YANKEE-ROWE)

AMENDMENT TO FACILITY OPERATING LICENSE

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Amendment No. 44 License No. DPR-3

l. _The Nuclear Regulatory Commission (the Commission) has found that:

A.

The applications for amendment by Yankee Atomic Electric Company (the licensee) dated September 8 and October 27, 1977, as supple-mented November 14, 1977, comply with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act), and

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the Commission's rules and regulations set forth in 10 CFR Chapter I;.

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B.

The facility will operate in conformity with the applications, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance.(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been' satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.

DPR-3 is hereby amended to read as follows:

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=,=.:."Y ise 5 (2). Technical Specifications

.j The Technical Specifications ' contained in Appendix A, as revised through Amendment No. 44

,~are hereby incorporated

rgsr-in the. license. Th; licensee shall: operate the facility E=~,

'in accordance with the Technical Specifications.

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This lice. rise amendment is effective a's of the date of its issuance.

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FOR THE NUCLEAR. REGULATORY COMMISSION

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A. Schwencer, Chief

=i Operating Reactors Branch #1

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Division of Operating Reactors

Attachment:

Changes to the Technical-

- Specifications Date of Issuance:

November 29, 1977 FM e4 e

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w TTACHMENT'TO' LICENSE AMENDMENT-49. 44

....== =g.1 FACILITY ~ LICENSE NO. DPR-3

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- DOCKET NO. 50-29 N

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. Revise Appendix A as follows:

g.=E" Remove-the following pages and insert revised pages:

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3/4 2 3/4-2-2

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3/4 2-3 -'3/4-2-4

..J 3/4 2 3/4 2-10 JE 3/4.5-1 3/4 5-2.

Marginal lines indicate revised area. Overleaf pages are provided

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for convenience.

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• .7:L 3/4.5 EMERGENCY CORE' COOLING SYSTEMS (ECCS) 3r ACCUMULATOR.

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LIMITING CONDITION FOR OPERATION' i_

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3.5.1 lThe low pressure safety injection accumulator shall be OPERABLE E

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Isolation valves SI-MOV-1 and SI-TV-608 open, b.

A minimum useable contained borated water volume of [00 cubic feet of borated water, equivalent to an indicated level. of 261" in the accumulator.

c.

~A mir.imum boron concentration of 2200 PPM,

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An accumulator nitrogen cover-pressure of-less than 15 g

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psig..

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e.

The nitrogen supply system with three supply pressure regulating W:J.5 Yalves set at 473+ 10 psig and at least:

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1.

Sixteen 48 cubic foot nitrogen bottles > i390 psig,.or 2.

Seventeen 48 cubic foot nitrogen bottles > 134O psig, or

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Eighteen 48 cubic foot nitrogen bottles > i294 psig.

3.

f.

Two OPERABLE low level venting system, and Timers set to operate between 4.'0 _+ 0.75 seconds.

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APPLICABILITY: MODES ~1, 2, 3* 4* and 5*

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ACTION:

a'.

With the accumula. tor. inoperable,.except as a result of a closed-isolation valve or as a resTilt of one-i'noper'able pressure regulating valve or one. inoperable low level venting system, restore the inoperable accumulator to OPERABLE status vithin 15 minutes cr be in at least H0T ' HUTDOWN with main coolant S

pressure'< 1000 r within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

b.

With the accumula.

inoperable due to one isolation valve being closed, either immediately open the isolation valve 'or be in at least HOT STANDBY within one hour and be in at least HOT SHUTDOWN with main coolant pressure < 1000 psig within the

.s next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

• Main coolant pressure > 1000 g.

Amendment 44-5-1 YANKEE-R0ut i

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EMERGEt'rY CORE COOLING SYSTEMS -

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LIMITIrlG CONDITION FOR OPERATION =(Continued)

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c.

With one inoperable supply pressure regulating valve or. with one

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inoperab'le lowflevel venting system, restore the inoperable regulating valve'or venting system to OPERABLE status within

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8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT STANDBY within one hour.and be in

_ 3:.g 4t least HOT SHUTDOWN with main coolant pressure < -1000 psig

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.:.3 within the following 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

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SURVEILLANCE REQUIREMENTS

=j 4.5.1 Th'e accumulator'shall be demonstrated OPERABLE:

a.

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by:

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1.

Verifying the contained borated water volume, accumulator nitrogencover-pressure and the supply pressure-regulator discharge pressure,'and 2

' Verifying that accumulator isolation valves SI-MOV-1 and

m SI-TV-608 are open.

b.

At least once per 31 days and within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after each solution yolume increase of-> 1% by. verifying the boron concentration of

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the accumulator soliition.

c.

At least once per 31 days by verifying the nitrogen supply

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d.

At least once per 18 months during shutdown by:

1.

. Verifying OPERABILITY of the nitrogen supply system by observing operation of each regulating valve.

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2..

Verifying OPERABILITY.of each low level venting system when the level switch column water level is lowered; at the same time, verify closure of SI-MOV-1 and SI-TV-608.

3.

Verify actuation of. each accumulator time delay relay.

The acceptable rundown time is 4.0 + 0.75 seconds.

l 4.

Verify that SI-TV-604, SI-TV-605 and SI-TV-606 open when

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l NS-S0V-46 is energized and again when NS-S0V-47 is energized'.

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YANKEE-ROWE 3/4 5-2 Amendment 44 j

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!E la y.=sg 3/4.2 POWER DISTRIBUTION LIMITS

=g PEAK LINEAR HEAT GENERATION RATE s

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.e LIMITING CONDITION FOR OPERATION g=

3'2.1 The peak linear heat generation rate-(LHGR) shall not exceed the 3AM

, limits of Figure-3.2-1 during steady state operat on in Cycle XIII.*

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i APPLICABILITY: MODE ~ 1 ACTION:

,...f is2 With the peak LHGR exceeding the ' limits of Figure 3.2-1; l

a'.. -Withiri'15 miriutes reduce' THERMAL POWER to no't n} ore' than that

_ [].7 fraction of the THERMAL POWER allowable for the main coolant pump l

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combination in operation, as expressed below:

Fraction of THERMAL POWER =

Limiting LHGR Peak Full Power LHGR

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b.

Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> reduce the Power Range and Intermediate Power Range Neutron Flux high trip setpoint to < 108% of the fraction

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of THERMAL POWER allowable for the main coolant pump combination.

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SURVEILLANCE REQUIREMENTS 4.2.l~1 The peak LHGR shall be determined to be within the limits of Figure 3.2-1 using incore instrumentation to obtain a power distribution map:

A.

Prior to initial operation above 75% of RATED THERMAL POWER after each fuel-loading, and

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i b.

At least once per 1,000 EFPH.

The provisions of Specification 4.'0.4 are not applicable.

c.

• 0peration in the 3-Loop mode is not permitted until appropriate LOCA analyses for this mode'have been approved by the NRC.

YANKEE-ROWE 3/4 2-1 Amendment 44

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POWER DISTRIBUTION LIMITS

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SURVEILLANCE REQUIREMENTS (Continued) i 4.2.1.2 The below factors shall be included in the cal.culation o~f ' peak

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full power LHGR:

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==k Heat flux power peaking factor, F'9, measured using incore

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instrumentation at a. power > 10%.

b.

Effect of inserting the control group from its position at the

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time of measurement to its insertion limit, F as shown in

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y Figure 3.2-2.

The rod insertion limit is shown in Figure 3.1-JE 1.

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c.

The multiplier for xenon redistribution is a function of core lifetime as given in Figure 3.2-3.

In addition, if control rod T.'h=5 Group C is inserted below 75 inches, allowable power may not be 75.:.::1

. regained until power has.been at a reduced level defined below for at least twenty four hours with control rod Group C g_

between 75 and 9.0 inches.

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Reduced power - allowable fraction of full power times raultiplier given in Figure 3.2-4.

Exceptions:

1.

If the rods are. inserted below 75 inches and power does not go below the reduced.

power calculated above, hold at the lowest

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attained power level for at least twenty.

=4 four hours with control rod Group C between 75 and 90 inches.before returning to

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allowable power.

2.

If' the -ods are inserted below 75 inches

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and zere power is held for more than 48 i

hours, no reduc.ed-power level need be held on the way to the allowable fraction of full power.

d.

Shortened stack. height factor,1.009.

lieasurement uncertainty, 1.'05.

c.

f.-

Power level uncertainty, 1.03.

E g.

Heat flux engineering factor, F,1.'04.

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Core average linear heat generation -rate at full power, 4.40 kw/ft.

l YANKEE-ROWE

i 3/4 2-2 Amendment No. 43 l

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POWER DISTRIBUTION LIMITS-

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SE=5 SURVEILLANCE REQUIREMENTS (Continued)

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4.2.1.3 LAt least once per 1000 EFPH the following limits shall bs 3===

determined by calculation not'to be exceeded at RATED THERMAL POWER:

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Hottest channel exit coolant temperature < 602*F, and b.

. Maximum clad surface temperature in hottest channel < 637*F.

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. 3/4 2-3' Amendment No. 43

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PO4ER DISTRIBUTION LIMITS ll:

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SURVEILLANCE REQUIREMENTS

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4.2.2.1 F shall be determined to be.within its limit by:

q a.

Using the movable incore detectors to obtain a power distribution map:

4" 1.

Prior to initial operation above 75% of RATED THERMAL POWER after each fuel loading, and 2.

aat least once per 1000 Effective Full Power Hours.

b.

Increasing the measured F component of the power distri-butionmapby4%toaccou8tforengineeringtolerances, increasing the value by 5% to account for measurement un.

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certaintics, and fLrther increasing the value by 3% to account for fuel densification.

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c.

The provisions of Specification 4.0.4 are not applicable.

4.2.2.2-When F is measured pursuant to Specification 4.10.2.2, an over-all measured F q hall be obtained from a power distribution map and in-s creased by 4% Eo-account for engineering tolerances, increased by SM to account for measurement uncertainity and further increased by 3% to account for fuel densification.

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~_"T YANKEE-ROWE 3/42-9 1

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POWER DISTRIBUTION LIMITS

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NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR - F H

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LIMITINC CONDITION FOR OPERATION 1

3.2.3 F shall be limited by the following relationship:

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II AH F

fl.80 [1.0 + 0.2 (1-P)]

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AH where P = THERMAL POWERRATED THERMAL POWER, and-APPLICABILITY: MODE 1 A=1 ACTION:

With F exceeding its limit:

aH a.

Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within ? hours and reduce the Power Range and Intermediate Power Range Neutron Flux-high trip setpoints to < 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, Demonstrate through in-core mapping that F"iYmit or educe is within its b.

limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding the THERMAL POWER.to less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, and c.

Identify and correct the cause of the out of limit condition prior to increasing THERMAL' POWER above the reduced limit required byaorb,aboyg;subsequentPOWEROPERATIONmayproceed provided that F is demonstrated through in-core mapping to.

be within its likit at a nominal-50% of RATED THERMAL POWER prior to exceeding this THERMAL POWER, at a nominal 75% of RATED THERMAL POWER prior to exceeding this THERMAL power and-within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after ' attaining 95% or greater RATED THERMAL POWER.

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YANKEE-R0WE 3/4 2-10 i

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