Text

Amend 172 to License DPR-52,revising Tech Specs for Cycle 6 Operation
	ML20248C868
Person / Time
Site:	Browns Ferry
Issue date:	09/13/1989
From:	Black S; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20248C873	List: ML20248C868; ML20248C884;
References
	NUDOCS 8910040049
	Download: ML20248C868 (13)
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c UNITED STATES 8-

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NUCLEAR REGULATORY COMMISSION 3

i WASHINGTON. D. C. 40555

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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 172 License No. DPR-52 1.

The Nuclear Regulatory Comission (the Commission')- has found that:

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated August 26, 1988, complies with the standards.and requirements of the Atomic Energy Act of 1954, as amended (the Act),

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

The facility will operate in confomity with the application, 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 comon defense and security or to the health and safety of the public; and E.

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

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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-52'is hereby amended to read as follows:

(2) Technical Specifications L

The Technical Specifications contained in Appendices A and B, as revised through Amendment No.172, are hereby incorporated in the license. The licensee shall operate the' facility in accordance with the Technical Specifications.

3.-

This license amendment is effective as of its date of issuance and shall be implemented within 90 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Suzanne ack, Assistant Director for Projects TVA Projects Division Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: September 13, 1989

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ATTACHMENT TO LICENSE AMENDMENT NO.172 FACILITY OPERATING LICENSE NO. DPR-52 DOCKET NO. 50-260' Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal.

lines indicating the area of change.. Overleaf pages* are provided to maintain document completeness.

REMOVE-INSERT 3.5/4.5-18 3.5/4.5 3.5/4.5-19 3.5/4.5-19*

3.5/4.5-20 3.5/4.5-20*

3.5/4.5-21 3.5/4.5-21 3.5/4.5-21a 3.5/4.5-21b 3.5/4.5-22 3.5/4.5-22 3.5/4.5-22a 3.5/4.5-22a.

3.5/4.5-30 3.5/4.5-10*

3.5/4.5-31 3.5/4.5-31 1

, - - - = _ - _ _. - _ - - - _. _ - - - - _ - _ _ - - _ - - -... _ - -

c trutvinc enunITIONS FOR TPERATION SURVEILLANCE REQUIREMENTS -3.5.I Avermaa Planar Linear Heat 4.5.I Marimum Averate P1maar Generation Rate l.

Linear Heat Generation Rate (MAPLHGR)

During steady-state power operation, The MAPLHGR for each type of.

the Maximum Average Planar Linear fuel as a function of average Heat Generation Rate (MAPLHGR) for planar exposure shall be each-type of: fuel as a function of determined daily during reactor.

average planar exposure shall not operation at 1 25% rated exceed the limiting value shown in-thermal power.

Tables 3.5.I-1, 2, 3, and 4.

If at

.any-time during operation it is determined by normal surveillance l

that the limiting value for MAPLHGR is being exceeded, action shall be initiated within 15 minutes to restore operation to within.the l

prescribed limits.

If the MAPLHGR is not returned to within' the.

prescribed limits within two (2) hours, the reactor shall bc brought to the Cold Shutdown condition

.within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . Surveillance and corresponding action shall continue until reactor. operation is within the prescribed limits.

J. Linear Heat Genera 11pn Rate (LHGR)

J.

Linear Heat Generation Rate (LEGR)

During steady-state power operation, The LHGR shall be checked the linear heat generation rate (LHGR) daily during reactor fuel of any rod in any fuel assembly at any operation at 1 25% rated axial location shall not exceed 13.4 thermal power.

kW/ft.

If at any time during operation it is determined by normal surveillance that the limiting value for LHGR is being exceeded, action shall be initiated v'ithin 15 minutes to restore operation to within the prescribed limits.

If the LHGR is not returned to within the prescribed limits within two (2) hours, the reactor shall be brought to the Cold Shutdown condition within 36 l

hours.

Surveillance and corresponding action shall continue until reactor operation is within the prescribed limits.

I BTN 3.5/4.5-18 Amendment No. 172 Unit 2 1

,3.5/4.5 rw** AND GNrfRDGEEFF

_ING SYSTEME 1,IMITING CONDITIONS FOR OPERATION SURVEIt--L"CE REQUIRBENTS 3.5.K Min *== critical Ps.i-r Ratl2 (MCFR) 4.5.K.

Minimum critical is r Ratio _(8E:PJt)

The minimum critical power ratio 1.

(MCPR) as a function of scram time MCPR shall be determined dai1Y and core flow, shall be oqual to or during reactor power operation greater than shown in Figure 3.5.K-1 at 2,25% rated thermal power multiplied by the Kg shown in and following any change in

{

rigure 3.5.2. where:

power level or distribution that would cause operation j

T= 0 or Tave T

with a limiting control rod B. whichever is pattern as described in the

.T'A-TB greater bases for Specification M.

T = 0.90 see (specification 3.3.C.1 A

2.

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scras time limit to 20% insertion The MCPR limit shall be deter-from fully withdrawn) mined for each fuel type 8x8.

8X8R. P8X8R from Figure 3.5.K-1. respectively. using:

-1

- g Ts = 0.~110+1.65 2 (0.053) [Ref.2]

n n

T;

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Tave = i=1 T= 0.0 prior to initial n

a.

scram time measurements number of surveillance rod for the cycle. Performed f

n=

tests performed to date in in accordance with cycle (including 30C test).

Specification 4.3.C.I.

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b.

fas defined in specifi-l Scram time to 20% insertion from cation 3.5.K following the fully withdrawn of the ith rod.

conclusion of each scram-I igt,gl number of active rods time surveillance test re-N=

measured in Specification quired by Specifications 4.3.C.1 at BOC.

4.3.C.1 and 4.3.C.2.

If at any time during steady-state The determination of the operation it is determined by normal limit must be completed surveillance that the limiting within "It hours of each value for MCPR is being exceeded, scram-time surveillance action shall be initiated within required by Specification 15 minutes to restore operation to 4.3.C.

within the prescribed limits.

If the steady-state MCPR is not returned to within the prescribed limits within two (2) hours. the reactor shall be brought to the Cold Shutdown condition within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months , surveillance and corresponding action shall continue I

until reactor operation is within the prescribed limits.

8PW Unit 2 3.5/4.5-19

i

' LIMITING CONDTTIONS TOR OPERATION SURVEIf.tlMCE REQUIREMENTS-i

.c 3.5 Core and Containment Coolina SVsta==

4.5 Core and Containment Coolina Systems-L.-APM9 EP,tDoints L.

APRM SetDoints 1.

Whenever the core thermal' Tk (FLPD shall be power is 1 25% of rated, the determined daily when ration of FRP/CMFLPD shall the reactor is 125% of be 1 1.0, or the APEM scram rated thermal power.

f and rod block setpoint equations listed in Sections 2.1.A and 2.1.B shall be multiplied by FRP/CMFLPD as follows:

SI'(0.66W + 54%) FRP CMFLPD SRBI (0.66W + 42%) (FRP

)-

CXFLPD 2.

When it is determined that 3.5.L.1 is not being met, 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months is allowed to correct the condition.

3.

If *.' L.1 and 3.5.L.2 cannot be met, the reactor power shall be. reduced to 1 25% of rated thermal power within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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l-BFN 3.5/4.5-20 Amendment No.' 143 L

Unit 2

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PAPLHGR YERSUS AVERAGE PLANAR EXPOSURE Fuel Type: P8DRB284L QUAD +

Average Planar:

Exposure MAPLHGR (mwd /t)

(kW/ft)-

a i

200 11.2 1,000 11.3.

5,000 11.8

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10,000 12.0.

15,000 12.0 20,000 11.8 25,000 11.2 30,000 10.8 i

35,000 10.2 40,000 9.5 45,000 B.8 Table 3.5.I-2

.MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE Fuel Type: P8DRF265H

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Average Planar Exposure PAPLHGR

(!"4d / t )

(kW/ft) 200 11.5 1

I 1,000 11.6

(

5,000 11.9 10,000 12.1 15,000 12.1 l

20,000 11,9 j

25,000 11.3 i

30,000 10.7 I

35,000 10.2 40,000 9.6 BTR 3.5/4.5-21 Amendment No. 172 Unit 2 l

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BFS 3.5/t. 5-21b Amendment NO. 172 Unit 2

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Tablo 3.5.I-3

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i MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE Fuel Type: P8DRB284Z Average Planar MAPLHGR

.Ernosure (mwd /t)

IkW/fti' 200 11.2

.1,000 11.2 5,000 11.7 10,000 12.0 15,000 12.0 20,000 11.8 25,000 11.1 30,000 10.4 35,000-9.8 40,000 9.1 45,000 8.5 Table 3.5.I-4 MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE Fuel Type:

BDRB284L Average Planar MAPLI:';R Exoosure (mwd /t)

(kW/ft) 200 11.2 1,000 11.3 5,000 11.8 10,000 12.0 l'5,000 12.0 20,000 11.8 25,000 11.2 30,000 10.8 35,000 10.2 40,000 9.5 BFN 3.5/4.5-21a Amendment No.172 Unit 2

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TAU Rcure 3.5.K ~

MCOR Limits for PS X ER/S X SR/ QUAD-BFN 3.5/4.5-22 Amendment No. 172 Unit 2

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1 BFS 3.5/4.5-22a Amendment No. 172 Unit 2

3.5 EASES (C:nt'd)

The p;ck cicdding terp;rnture felltwing a p:stulated loss-of-coolant accident is primarily a function of the average heat generation rate of all the rods of a fuel assembly at any axial location and is only dependent secondarily on the rod-to-rod power distribution within an assembly.

Since expected local variations in power distribution within a fuel assembly affect the calculated peak clad temperature by less than i 20*F relative to the peak temperature for a typical fuel design, the limit on the average linear heat generation rate is sufficient to assure that calculated temperatures are within the 10 CFR 50 Appendix K limit. The limiting value for MAPLHG7 is ssown in Tables 3.5.I-1, 2, 3, and 4.

The analyses supporting these limiting values are presented in Reference 1.

3.5.J. Linear Heat Generation Rate (LRGR)

This specification assures that the linear heat generation rate in any rod is less than the design linear heat generation if fuel pellet densification is postulated.

The LEGR shall be checked daily during reactor operation at 1 25 percent power to determine if fuel burnup, or control rod movement has caused changen in power distribution. For LHGR to be a limiting value below 25 percent rated thermal power, the R factor would have to be less than 0.241 which is precluded by a considerable margin when employing any permissible control rod pattern.

3.5.K. Minimum Critica! Power Ratio (MCPR)

At core thermal power levels less than or equal to 25 percent, the reactor will be operating at minimum recirculation pump speed and the moderator void content will be very small. For all designated control rod patterns which may be employed at this point, operating plant experience and thermal hydraulic analysis indicated that the resulting MCPR value is in excess of requirements by a considerable margin.

With this low void content, any inadvertent core flow increase would only place operation in a more conservative mode relative to MCPR.

The daily requirement for calculating MCPR above 25 percent rated ther=al power is sufficient since power distribution shifts are very slow when there have not been significant power or control rod changes.

The requirement for calculating MCPR when a limiting control rod pattern is spp' roached ensures that MCPR will be known following a change in power or power shape (regardless of magnitude) that could place operation at a thermal limit.

3.5.L. APRM Setooints Operation is constrained to a maximum LHGR of 13.4 kW/ft for 8x8 fuel.

This limit is reached when core =aximum fraction of limiting power density (CMFLPD) equals 1.0.

For the case where CMFLPD exceeds the fraction of rated thermal power, operation is permitted only at less than 100-percent rated power and only with APRM scram settings as required by Specification 3.5.L.1.

The scram trip setting and rod block trip setting are adjusted to ensure that no combination BFN 3.5/4.5-31 Amendment No. 172 Unit 2

+

l 3.5 BASES (Cant'd)-

Because the automatic depressurization system does not provide makeup I

to the reactor primary vessel, no credit is taken for the steam cooling of.the core caused by the system actuation to provide further conservatism to the CSCS.

[

With two ADS valves known to be incapable of automatic operatien, four valves remain OPERABLE to perform their ADS function.

The ECCS loss-of-coolant accident analyses for small line breaks assumed that four of the six ADS valves were OPERABLE. Reactor operation with three ADS valves inoperable is allowed to continue for seven days provided z

that the HPCI system is OPERABLE. Operation with more than three of the six ADS valves inoperable is not acceptable.

3.5.H. Maintenance of Filled Discharge Ploe If the discharge piping of the core spray, LPCI, HPCIS, and RCICS are not filled, a water hammer can develop in this piping when the pump and/or pumps are started.

To minimize damage to the discharge piping and to ensure added margin in the operation of these systems, this Technical Specification requires the discharge lines to be filled whenever the system is in an OPERABLE condition.

If a discharge pipe is not filled, the pumps that supply that line must be assumed to be inoperable for Technical Specification purposes.

The core spray and RHR system cischarge piping high point vent is visually checked for water flow once a month and prior to testing to ensure that the lines are filled. The visual checking vill avoid starting the core spray or RHR system with a discharge line not filled.

In. addition to the visual observation and to ensure a filled discharge line other than prior to testing, a pressure suppression i

chamber head tank is located approximately 20 feet above the discharge line high point to supply makeup water for these systems. The condensate head tank located approximately 100 feet above the discharge high point serves as a backup charging system when the pressure suppression chamber head tank is not in service.

System discharge pressure indicators are used to determine the water level above the discharge line high point.

The indicators vill reflect approximately 30 psig for a water level at the high point and 45 psig for a water level in the pressure suppression chamber head tank and are monitored daily to ensure that the discharge lines are filled.

When in their normal standby condition, the suction for the HPCI and RCIC pumps are aligned to the condensate storage tank, which is physically at a higher elevation than the HPCIS and RCICS piping.

This assures that the HPCI and RCIC discharge piping remains filled.

Further assurance is provided by observing water flow from these systems' high points monthly.

3.5.I. Maximum Averare Planar Linear Heat Generation Rate (MAPLHGR)

This specification assures that the postulated design basis loss-of-coolantthe peak cladding temperature following accident vill not exceed the limit specified in the 10 CFR 50, Appendix K.

BFN 3.5/4.5-30 Unit 2 Amendment No. 169

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ML20248C868

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