ML18025B977

Proposed Tech Spec Changes Allowing Operation W/Increased Core Flow

ML18025B977
Person / Time
Site:	Browns Ferry
Issue date:	06/02/1983
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18025B976	List: ML18025B975 ML18025B977
References
NUDOCS 8306160456
Download: ML18025B977 (23)

Text

ENCLOSURE 1

PROPOSED TECHNICAL SPECIFICATION REVISIONS TVA BFNP TS 188 BROWNS FERRY NUCLEAR PLANT UNITS 2 AND 3 830bib045b 830b02 PDR ADOCK 050002b0 P

PDR

k, A

l(

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Kinisun boi operable Per

~ac<

s

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S tenetion TABES 3.3ic IHSTROlCEHTLTIOI T4LT IHITIATES R00 BLOCKS Tri tewel Set 3(1) 3 (1) 3 (1) 1(1) (C) 2(l) (6) 3 (1) (6) 1(1) (6)

APSE Upscale (tice Bias)

APED Upscale (Startup Node)

(8)

APSE Downscale (9)

ApRK Inoperatiee RNl Upscale (Plov bias)

Rb}( Doenac ale (9)

SSW Inoperatiee auC Upscale (8)

IRS Domscale (3) (8)

Wt Detector not in Startup Position (8) 1)N Inoperatiee (8)

SRS Upscale (8)

SN Doenscale (8) (8)

~0.66uoalb (1) e 118

~ 3%

(10D)

< 0. 66siaoS (I) {13)

(lbc)

~ 108/11$ of full scale

+ $/11$ of full scale (10a)

S T'r 10 counts/sec.

~ 3 counts/sec.

SRH Inoperatiee (8)

Ploe bias Coaparator Piov bias Upscale bod block )ogle (10 a) 101 difference in recirculation flove

<11M recirculation flow S/A sRll Detector not in startup position (a) (8)

(ll)

RSCS Restraint (PS-8$ -ClA an4 PS-8$ -C1S) 187 psig turbine first-stage pressure 1(12)

Scram D(scharge Tank Mater Level lllgh

~25 gaI.

V

d.

This function is bypassed vhsn the cade svitch is placed io Run.

9.

Thfs function ts only nctlvo vhsn tho redo svttch is in Run.

This funct ton 1d automat !cally bypassed vhon tho 1RH instrumentation io operable snd not high.

10, Tha inoperative trips src produced by tha folloving functions:

~,

SRK and JRH (1)

Local "oporatemslibratc" svitch not in operate

(2)

Povor supply voltage lov.

(3)

Circuit boards not in circuit.

b.

APRH (1)

Local "operate-cslibrsc

~ " r~itch not in opsrato, (2)

Lsss chan 14 LPRH inputs'3)

Circuit boards not in circuit.

c.

RRH (1)

Local "operate-calibrato" svitch not in oparata.

(2)

Circuit boards not in circuit.

(3)

RSH fails to null.

(4)

Less than required number of LPRH inputs for rod aalacted.

11.

Detector troversc ts sd )usted to 114 - 2 inches, placing the

+

detector lover post cion 24 inchea below the lover coro plato.

12, This function may bc bypassed in'he shutdown or refuel mode.

Ef this function is inoperable at a time when operability is required the channel shall be tripped or administrative controls shall be immediately imposed to prevent control rod withd awal.

13.

RBM upscale flow biased setpoin't clipped at 106% rated reactor S

power.

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0.0 041 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0'igure 3.5.K-l MCPR LIMITS 172a

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BRONNS FERRY NUCLEAR PLANT FIGURE 3.5.2

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Kf FACTOR I.2 AUTOMATiC FLOVl CONTROL Kg I.0 MANUALFLOVf CONTROL Scoop-Tube Set-Point Calibration position such that Flowmax

= 102;5 7 107.0 /

112.0 %~

1 1 V.0'/

30 40 50 60 70 CORE FLON,N

• Kf = l.0 for core flow >100%.

0 0

Kin(sue So.

Oparanla Per S

punction TABLE Io 2eC IKSTROKZKTATIGtlTBAT IKITIATES ROD BLOCKS Zr{

Level Sst 2 {1) 3 (1) 3 (1) 3 {1) 2(1) {6) 2{1) {6) 2l1) {6) 2{1) {6)

APRK Upscale (Ply Blas)

APRK Opscale (Startup Kode)

(8)

APRK Damscale (9)

APRK Inoperative RBK Opscale (tlov Bias)

RBK Dovnscale (9)

RBK Inoperative IRK Opscale (8)

IRK Dovnecale

{3) (8)

IRK Detector not (n Startup position (8)

IRK Inoperative'8)

SRK Opscale (8)

SRK Oovnscale

{a) (8)

~0.66Mia28

{2)

~ 125

~35 (10b)

< 0.66Kas05 (2) (].3)

~ 35 (10c) 5 108/125 of tall scale

+ 5/125 of full scale (10a)

-1 r 10 counts/sac.

c 3 counts/sec+

SRK Inoperative

{4)

Plov Bias Cosparator Plod Bias Upscale Rod Block Logic (10a) 105 difference ln recirculation floes

< 115% recirculation flow R/A sRK Detector not in Startup Position

( ~) (8)

(11) 2 (1) 1(12)

RSCS Restraint

{PS-85 61h and PS 8$ 61B)

Scran Discharge Tank Mater

. Level High 187 psig turbine first-etage pressure C25 gal.

U

The s function is bypassed when the mode switch is placed in Run.

9.

This function is only active when the mode switch is in Run.

Thzs tunctzon is automatically bypassed when the IRN instr um ~ntat.son is oper able and not high.

10.

The innoerat iv> trips are produced by the followinq f unct lo<<s:

a.

S<<M and

) RN

{ ))

Loca)

"opi. r <t~-calibrate" sws t ch no<

xn operate.

pnv<rr sunni v vol <.ace low.

(3)

C~rcuxt boards not in circuxt.

b.

A PRN (1)

Local "operate-calibrat,e" switch not in operate.

(2)

Less than 14 LPRM inputs.

(3)

Circuit boards not in circuit.

c.

RBN'ocal "operate-calibrate" switch not in operate.

(2)

Circuit boards not in circuit.

(3)

RBN fails to null.

(4)

Less than required number of LPRN input.s for rod selected.

11. Detector traverse is adjusted to 114

+

2 inches, placing the detector lower position 24 inches below the lower core plate.

12.

This function may be bypassed in the shutdown or refuel,mode.

If this bl ti e when operability is required the channel shall be tripped or administrative controls shall be immediately mpose to prevent 'control rod withdrawal.

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13.

RBM upscale flow biased setpoint clipped at 106% rated reactor power.

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0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 Figure 3.5.K-1 MCPR LIMITS*

• NOTE:

Lead test assemblies are categorized as PSx8R bundles.

182b

~

~

BROV/NS FERRY NUCLEAR. PLANT

~

~

F lQUR E 3.5.2-K] FACTOR.

l.2 AUTOMATlC FLOW CONTROL Kf l.0 MANUAL FLOiV CONTROL Scoo p-Tuba Set-Point Calibration position avch that Flo @max " 102;5'4 107.0 'I 112-0%

117.0 '/

- ~

30 40 50 60 70 CORK FLOW,W 90

• Kf = 1.0 for core flow > 100%.

~

'e

ENCLOSURE 2 DESCRIPTION AND JUSTIFICATION OF TECHNICAL SPECIFICATION CHANGES TVA BFNP TS 188 BROWNS FERRY NUCLEAR PLANT UNITS 2 AND 3 DESCRIPTION OF CHANGES Pa es 73 (unit 2 and 76 (unit 3)

Add note 13 and increase flow bias upscale to <115 percent recirculation flow.

Pa es 75 (unit 2) and 78 (unit 3)

Add note 13.

Pa es 172a (unit 2) and 182b (unit

)

Revise MCPR tables.

Pa es 173 (unit 2) and 183 (unit

)

Add footnote to 100 percent core flow.

JUSTIFICATION The proposed revisions are needed to facilitate operating units 2 and 3

with increased core flow.

NEDO-22245 and NEDO-22149 are safety evaluations per formed by General Electric Company to show that Browns Ferry units 2 and 3, respectively, can operate in the condition specified.

The limiting abnormal operational transients for rated-flow, operation and the loss of coolant accident, rod drop accident, and'rod withdrawal error events were reanalyzed for increased core flow operation.

The above safety evaluations showed that the MCPR operating limits increased by a slight margin.

The graphs on page 172a of the unit 2 technical specifications and page 182b of the unit 3 technical specifications are revised to reflect this change.

The reports also specify the following operational conditions necessary to operate in an increased core flow condition.

I

The rod block monitor upscale (flow biased) must be "clipped" at 106-percent power in order to ensure adequate protection in the event of a rod withdrawal error.

A note is being added to table 3.2.C to reflect this.

Also in this table, the rod block on recirculation flow is being increased from 110 percent to 115 percent to ensure operational flexibility.

A note is being added to figure.3.5.2 to reflect that the Kf is equal to 1.0 for core flows greater than or equal to rated core flow.

All other operating limits previously established for the unit 2 cycle 5

reload licensing bases and the unit 3 cycle 5 reload licensing bases have been shown in the respective General Electric NEDOs to be bounding.

4 t

ENCLOSURE 3 SIGNIFICANT HAZARDS CONSIDERATION FOR PROPOSED TECHNICAL SPECIFICATION CHANGE TVA BFNP TS 188 BROWNS FERRY NUCLEAR PLANT UNITS 2 AND 3 1.

Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?

No.

NEDO-22245 and NEDO-22149 are safety evaluations performed by General Electric Company which show that Browns Ferry units 2 and 3, respectively, can operate with increased core flow.

The limiting abnormal operational transients for rated flow operation and the loss of coolant accident, rod drop accident, and rod withdrawal error events were reanalyzed for increased core flow operation.

The reanalysis showed that the MCPR operating limits increased by a slight margin.

All other operating limits previously established for the unit 2 cycle 5 reload licensing bases and the unit 3 cycle 5

reload licensing bases have been shown in the respective NEDOs to be bounding.

2.

Does the proposed amendment create the probability of a new or different kind of accident from any accident previously evaluated?

No.

The revisions facilitate operating with an increase in core flow.

This mode of operating does not create the possibility of a new or different kind of accident from any accident previously evaluated.

All accidents have been evaluated in the above NEDOs.

3 ~

Does the proposed amendment involve a significant reduction in a margin of safety?

No.

As stated in (1), the operating limits previously established for cycle 5 for units 2 and 3 are bounding.

MCPR does increase slightly, and the proposed revisions reflect this.

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