ML20203K807

Rev 0 to Training Lesson Plan LO-LP-39203-00, Safety Limits & Limiting Safety Sys Settings

ML20203K807
Person / Time
Site:	Vogtle
Issue date:	08/01/1986
From:	Brown R, Slough R GEORGIA POWER CO.
To:
Shared Package
ML20203K798	List: ML20203K796 ML20203K800 ML20203K804 ML20203K807 ML20203K808 ML20203K812 ML20203K816 ML20203K820 ML20203K823 ML20203K827 ML20203K832 ML20203K833 ML20203K836 ML20203K839 ML20203K844 ML20203K848 ML20203K850 ML20203K854 ML20203K858 ML20203K861 ML20203K863 ML20203K866 ML20203K870 ML20203K873 ML20203K878
References
LO-LP-39203, LO-LP-39203-00, NUDOCS 8608210348
Download: ML20203K807 (13)

Text

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VOGTLE ELECTRIC GENERATINGfLANF-L k

! TRAINING LESSON PLAN -

TITLE: y S ggmITS AE LIMITING SAFETY SYSTM NUMBER: LO-LP-39203-00 PROGRAM: LICENSED OPERATOR TRAINING 0 REVISION-AUTHOR: R. SLOUGH DATE: 8/1/86 APPROVED: M h[g DATE:

f/r/[C INSTRUCTORGUIDELINE[:

1. OVERHEAD TRANSPARENCY MACHINE

2. WHITE BOARD AND MARKERS

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8600010340 G60314 I

PDR ADOCK 05000424 V PDR 1

LO-LP-39203-00 PURPOSE STATEMENT:

1.

TEACH THE STUDENT THE APPLICABILITY AND ACTIONS STATEMENTS OF SAFETY LIMITS AhT L.S.S.S.

II. LIST OF OBJECTIVES:

1. Students will be able to determine if,they are exceeding the core safety limit curve.

2. The students will be able to give the setpoints for the RCS pressure safety limit and all L.S.S.S.

3. The student will know the action requirements from memory for exceeding any safety limit.

4. The student should be familiar with the reactor core safety ifait curve.

5. SRO students should be able to explain the bases for each section of the reactor core safety limit curve.

, 2 1

-- LO-LP-39203-00

REFERENCES:

1. TECHNICAL SPECIFICATIONS SECTION 2 SAFETY LIMITS & L.S.S.S i 2. FSAR CHAPTER 15 t

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LO-LP-39203-00

Ill. LESSON OUTLINE: NOTES I. PRESENTATION A. Safety Limits 6

1. Basesforsafetylimitsin10CFR50.3f' a) Protect b*rriers a against release

2. Core Safety Limits

a. Designed to protect fuel clad

b. Based on two characteristics

1) Power level of fuel

2) Heat transfer capability of water a) Temperature - Tave b) Pressure of RCS l

c. Tech Spec. 2.1.1 d d 'r.

<: - LO-TP-39203-00-001 C.p ,<. u~s ~~

1) Cbabination of power pressure and Tavs

_not, exceed limits

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d. T. S. 6.7.1 .

1) Reporting requirements for Safety Limit violation

e. Bases for curve, Section 1

1) Low power level of curve a) Corresponds to TH ** ***"#**I**

b) Delta-T is no longer valid indication of power I

c) OPdeltaT and OTdeltaT no longer provide protection

f. Bases for curve Section 2

1) DNBR of 1.30 at 15% quality

2) only limiting at high pressures l

l 4

LO-LP-39203-00 lli. LESSON OUTLINE: NOTES

3) Ask why DNBR of 1.3 is bad

4) As long as DNBR is greater than or equal l to 1.3 1 a) ,

95% of fuel is not experiencing DNB b) At a 95% confidence level (95/100 tests)

5) DNB drives down heat transfer coefficient a) Fuel temperature increases b) Clad damage likely

g. Bases for curve, Section 3 DNBR of 1.30

h. Restrictions of curve

1) Only applicable to 4 loop flow a) P-8 base"d on staying within curve on RCP trip b) Delta-I within the target band

i. Protection Provided

1) S/G safeties protect at low powers

2) OTdeltaT and P.R. high flux protect at high powers

3) OTdeltaT protects.open area not protected by others a) Lowers setpoint as delta-1 exceeds band b) Lovers setpoint as Tave increases c) Lovers setpoint as pressure decreases

3. RCS Pressure Safety Limit

a. Designed to protect the RCS integrity

b. Based on limiting maximum RCS pressure j

5

LO-LP-39203-00 Ill. LESSON OUTLINE: NOTES

c. Read 2.1.2 RCS Pressure Safety Limit

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d. Actions for Modes 3, 4, and 5 more restrictive pr. - -

1) Brittle fracture more likely at lov temperature

e. Protection Provided

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1) Pressurizer code safety valves ,

a) Lift settings of 2485 psig B. Limiting Safety System Setpoints

1. Purpose

.t . Prevent reaching Rx core and RCS safety limits during:

1) Normal operations

2) Design bases anticipated operational occurrences ,

b. Assist ESFAS in mitigating accidents

2. Reactor Trip System Instrumentation

a. Manual reactor trip

1) Bases - gives operator manual trip capability

b. Power Range neutron flux

1) High setpoint ;f' ,109%

a) Allowable value - f 111.1%

2) Low setpoint {,25%

a) Allowable value - ;f[27.1%

3) Bases a) Low setpoint - provide protection against a power excursion from low power levels.

6

LO-LP-39203-00 III. LESSON OUTLINE: NOTES b) High setpoint - provide protection against a power excursion from low power levels.

c. Power Range neutron flux high positive rate

1) Setpoint - 15% / 2 seconds

2) Allowable value - i 6.3%/ 2 seconds

3) Bases - rod ejection accident

d. Power range neutron flux high negative rate

1) Satpoint - f 5%/ 2 seconds

2) Allowable value - f 6.3% / 2 seconds

3) Bases - prevent excessive local flux peaking resulting in DNBR< 1.3 for all single or multiple dropped rods.

e. Intermediate Range High Flux -

1) Setpoint - 1 25%

2) Allowable value - 130.9%

3) Bases - uncontrolled rod withdrawal from suberitical condition

f. Source Range High Flux a m m .. -

1) Setpoint - i 1 x 10 cps '

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(2) Allowable value - f 1.4 x 10 eps

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3) Bases - same as IR 3 OT delta I

, 1) Setpoint - variable

2) Allowable value _ setpoint + 2.6%

3) Bases - DNB protection for slow transients with pressure in band.

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LO-LP-39203-00 Ill. LESSON OUTLINE: NOTES

h. OP delta T

1) Setpoint - variable

2) Allowable value - f setpoint + 3.6%

3) Basek - has three a) Protect fuel integrity b) Limits required range of OT delta T c) Backup to PR High Flux high setpoint

1. Pressurizer low pressure

1) Setpoint - 1 1960 psig

2) Allowable value - 1 1948 psig

3) Bases - DNB protection J. Pressuriser high pressure

1) Setpoint-I2385psig

2) Allowable value - < 2397 psig

3) Bases - protect RCS integrity

k. Pressurizer high level

1) Setpoint - f 92%

2) Allowable value - i 93.8%

3) Bases - prevent water relief through Code Safeties.

1. Loss of flow

1) Setpoint - 1 90% of design loop flow

2) Allowable - 1 88.7% of design loop flow

3) Bases - DNB protection 8

LO-LP-39203-00 2 111. LESSON OUTLINE: NOTES

m. S/G low - low level

1) Setpoint - 1 17% N.R.

2) Allowable value - 1 15.3% N.R.

3) Base's - prevent loss of heat sink

n. RCP undervoltage

1) Setpoint - 1 70% bus voltage (9660 vac)

2) Allowable value - 1 69% bus voltage (9522 vac)

3) Bases - DNB protection

o. RCP underfrequency

1) Setpoint - 2 57.2 H 2

2) Allowable - 1 57.1 H 2

3) Bases - DNB Rrotection

p. Turbine trip

1) Setpoints a) ETS Fluid low pressure - 1 600 psig b) Turbine Stop Values closure -

1 97.6% open

2) Allowable values a) ETS finid low pressure - 1 500 psig b) Turbine stop values closure -

1 97.6% open

3) Bases - initiate reactor trip, no other bases given

q. SI input from ESF

1) Bases - backup to RPS on accident 9

LO-LP-39203-00

Ill. LESSON OUTLINE: NOTES

3. Reactor Trip System Interlocks

a. P-6

-0

1) Setpoint _ 1x10 Amps

2) Allowable _ 6 x 10" " Amps

3) Bases - allow manual block of SR high flux trip and deenergize SR detectors.

b. P-7

1) Satpoints a) Input from P-10 b) Input from P-13

2) Bases - below setpoint, blocks five reactor trips, a) Low flow in more than one loop b) RCP undervoltage c) RCP underfrequency d) Pressurizer low pressure a) Pressurizer high level _

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3) Bases - blocks low flow trip in more than one loop g-

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d. . JV -- - f Setpoint _ 48% power w _. ..

2) Allowable _ 30.Z power

3) Bases - Blocks reactor trip or turbine trip 10

LO-LP-39203-00

.- lil. LESSON OUTLINE: NOTES

e. P-10

1) Setpoint - ]> 10% power ,

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2) Allowable value - j23 1.,8% power

3) Base's - blocks intermediate and power range low S.P. trips; input to P-7

f. P-13

1) Setpoint j( 10% Turbine power I

2) Allowable  ; 2000 PSIA 3

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O, 0.2 0.4 0.8 0.8 1.0 1.2 s FRACTION OF RATED THERMAL POWER Figure 2.1-1. Reactor Core Safety Limits l l[ l Vo S n c - a m r .t ,_, LG- TP- 397us- go-ec j

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LOCUS OF CONDITIONS WHERE g POWER = 118% OF NOMINAL 70 -

POWER JT pa 5

\ TRIP LINE 65 - 1 2000 )

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CONDITIONS I (

WHERE DNBR = 1.3 f 50 -

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OVER-l TEMPERATURE l AT TRIP LINES 40 -

LOCUS OF CONDITIONS WHERE STEAM 35 -

GENERATOR SAFETY VALVES OPEN 30  !  !  !  !  ! l l 560 570 580 590 600 610 620 630 640 T ag ( F) i to -rp- 3m 3_ oc - oc 7_

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