Text

Corrected Amend 30 to License NPF-39 Re Limiting Condition for Operation & Surveillance Requirements for APRM Setpoints,Min Critical Power Ration,Control Rod Withdrawal Block Instrumentation & Recirculation Loops
	ML20248E562
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Site:	Limerick
Issue date:	09/18/1989
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POWER DISTRIBUTION LIMITS 3/4.2.2 APRM SETPOINTS j.

LIMITING CONDITION FOR OPERATION 3.2.2 The APRM flow biased neutron flux-upscale scram trip setpoint (S) and flow biased neutron flux upscale control rod block trip setpoint (SRB) shall be established according to the following relationships:

TRIP SETPOINT During two recirculation 5 < (0.58W + 59%)T.

ALLOWABLE VALUE 5'< (0.58W + 62%)T loop operation S

5 (0.58W + 50%)T Sj$(0.58W+53%)T R

R During single recirculation S < (0.58W + 54%)T S < (0.58W + 57%)T loop operation Sf1(0.58W+45%)T Sfi(0.58W+48%)T R

R where:

5 and S are in percent of RATED THERMAL POWER, RB W = Loop recirculation flow as a percentage of the loop recirculation flow which produces a rated core flow of 100 million lbs/hr, T = Lowest value of the ratio of FRACTION OF RATED THERMAL POWER divided by the CORE MAXIMUM FRACTION OF LIMITING POWER DENSITY.

T is applied only if less than or equal to 1.0.

APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER.

ACTION:

With the APRM flow biased neutron flux-upscale scram trip setpoint and/or the flow biased neutron flux upscale control rod block trip setpoint less conservative than the value shown in the Allowable Value column for S or l

5 as above determined, initiate corrective action within 15 minutes a$, adjust 5and/ ors to be consistent with the Trip Setpoint values

pg within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or reduce THERMAL POWER to less than 25% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

SURVEILLANCE REQUIREMENTS 4.2.2 The FRTP and the MFLPD shall be determined, the value of T calculated, and the most recent actual APRM flow biased neutron flux upscale scram and flow biased neutron flux-upscale control rod block trip setpoints verified to be within the above limits or adjusted, as required:

a.

At least once'per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months af ter completion of a THERMAL POWER increase of at least 15% of RATED THERMAL POWER, and Initially and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the reactor is operating c.

with MFLPD greater than or equal to FRTP.

d.

The provisions of Specification 4.0.4 are not applicable.

With MFLPD greater than the FRTP, rather than adjusting the APRM setpoints,

[

the APRM gain may be adjusted such that the APRM readings are greater than or equal to 100% times MFLPD, provided that the adjusted APRM reading does not exceed 100% of RATED THERMAL POWER and a notice of adjustment is posted on the reactor control panel.

LIMERICK - UNIT 1 3/4 2-7 Amendment No. 7, 30 l

8910050290 090918 DR ADDCK 0500 2

i POWER DISTRIWTION LIMITS 3/4.2.3 NINDtM CRITICAL POWER RATIO LIMITING CONDITION FOR OPERATION 3.2.3 than the MCPR limit shown in Figure 3.2.3-la (BP/P8X8 3.2.3-lb (BP/P8X8A fuel), Figure 3.2.3-ic (GE SX8E8 fuel) an)d Figure 3.2.3 (GE 8X8E8 fuel) times the K end-of-cycle recirculation p, ump trip (E0C RPT) system is OPERA Specification 3.3.4.2, with:

dave I )

B ta tgtg where:

g = 0.86 seconds, control rod averap scras insertion i

time limit to notch 39 per Spec 1fication 3.1.3.3, N

I N

rg = 0.672 + 1.65[

J(0.015),

n I "i ist n

l I

t,,,,

g,3 N tg g

n I

NI i=1 n = number of surveillance tests performed to date in cycle, Ng a number of active control rods measured in the i surveillance test, 19 = average scram time to notch 39 of all rods measured l

th in the i surveillance test, and Ng = 4.1.3.2.a. total number of active rods measured in Specification APPLICA8ILITY:

OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to' 25% of RATED THERMAL POWER.

LIMERICK - UNIT 1 3/4 2-8 Amenepnt No.

19 l

AFR :.; 1999 b_______________--___.

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TA8tf 3.3.6 1 (Continued)

Coitteet e00 v!TetasmL BL0ct Insteuntwist!m ACTION $7Atta wft ACT!Dn 60 Declare the ROM inneerable and tah the ACTION reestred by Seecificatten 1.1.4.3.

ACT]DN 61 With the nusher of.0Pt448Lt channels one se more less then resulHM by the Nintaus opt 448LE channels per Trip Funciten reell N ont, place et least one tasperatie thennel in the tripp M tenettien within ene have.

ACTION $3 -

With the numer of GPERABLE channels less than reevired by the Mtnicum opt 4A8LE Channels per Trip Funetten reevirement, piece the ihaperatie channel in the tripped genditlen within one hour.

ACTION 63 With the number of Opt 4ABLE channels'less than reevired by the Minleva opt 4ABLt Channels per Trip Functlen requirensat, taittate a res tiott.

Elli With TMthtL POWER > 38 ef RAftp TMEMAL POWtt.

with more than one control red withdreen. Not applicable is centrol rods rwered per Speciffsatten 3.9.10.1 or 3.f.10.2.

These thannels are not reevired when stateen er fewer fuel asseelfes.

.esjecent to the $ ms, are is the core.

(a) The atM shall be evtanatica11y typassed when a peripheral control ret is selectes or the reference APM thennel inetcates less than 3 8 of 4AT[D fut mat POWER.

(6) This function shall be automatically typessed if detector asunt reta is

> 100 ses or the I m shonnels are en range 3 or higher.

(c) This fumetten is autenettsally bypassed when the assettated !R enannels are sa range 4 er hipter.

(g) This fumetteh is autenettsally bypassed when the I m thannels are en rangs 3 er higher.

(e) This function is anteestissily typassed when the IW thannels are en i

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3/4.4 REACTOR COOLANT SYSTEM "3/4.4.1 RECIRCULATION SYSTEM RECIRCULATION LOOPS

-LIMITING CONDITION FOR OPERATION 3.4.1 1 Two. reactor coolant system recirculation loops shall be in operation with:

Total core flow greater than or equal to 45% of rated core flow, or a.

b.

THERMAL POWER within the unrestricted zone of Figure 3.4.1.1-1.

[

APPLICABILITY: OPERATIONAL CONDITIONS 18 and 2*.

ACTION:

With one reactor coolant system recirculation loop not in operation:

a.

1.

Within 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months s:

a.

Place the recirculation flow control system in the Local -

Manual mode, and b.

Reduce THERMAL POWER to i 70% of RATED THERMAL POWER, and, c.

Reduce the Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) limit to a value of 0.89 times the two recirculation loop operation limit per Specification 3.2.1, and, d.

Limit the speed of the operating recirculation pump to less tha.n or equal to 90% of rated pump speed, and e.

Verify that the differential temperature requirements of Surveillance Requirement 4.4.1.1.5 are met if THERMAL POWER is < 30% of RATED THERMAL POWER or the recirculation loop flow in the operating loop is 1 50% of rated loop flow, or suspend the THERMAL POWER or recirculation loop flow increase.

See Special Test Exception 3.10.4 LIMERICK - UNIT 1 3/4 4-1 Amendment No. 30 l

l

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ~ _ _ _ _ _ _ _ _ _ _ _ _ _ - _

j

/

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+

' REACTOR COOLANT SYSTEM LIMITING CO W ITION FOR OPERATION (Continued)

ACTION:

(Continued) 2.

Within 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months s:

Reduce the Average Power Range Monitor (APRM). Scram and Rod l

Block,'and Rod Block Monitor Trip Setpoints and Allowable i

Values, to those applicable for single recirculation loop i

operation per Specifications 2.2.1,-3.2.2, and 3.3.6, or L

declare the associated channel (s) inoperable and take the actions required by the referenced specifications, and, j

L 3.

The provisions of Specification 3.0.4 are not applicable.

4.

Otherwise be in at least NOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

i With no reactor coolant system recirculation loops in operation, I

b.

immediately initiate action to reduce THERMAL POWER such that it is i

not within the restricted zone of Figure 3.4.1.1-1 within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and initiate measures to place the unit in at least STARTUP within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTOOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

With one or two reactor coolant system recirculation loops in i

c.

i operation and total core flow less than 455 but greater than 39% of rated core flow and THERMAL POWER within the restricted zone of i

Figure 3.4.1.1-1:

1.

Determine the APRM and LPRM** noise levels (Surveillance 4.4.1.1.3):

1 a.

At least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , and l

b.

Within 30 einutes after the completion of a THERMAL POWER increase of at least 5% of RATED THERMAL POWER.

4 2.

With the APRM or LPRM** neutron flux noise levels greater than f

three times their established baseline noise levels, within 15 minutes initiate corrective action to restore the noise levels i

within the required limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months by increasing core i

flow or by reducing THERMAL POWER.

i d.

With one or two reactor coolant system recirculation loops in i

operation and total core flow less than or equal to 39% and THERMAL 1

POWER within the restricted zone of Figure 3.4.1.1-1, within 15 minutes initiate corrective action to reduce THERMAL POWER to within the. unrestricted zone of Figure 3.4.1.1-1 or increase core flow to l

greater than 39% within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

"" Detector levels A and C of one LPRM string per core octant plus detectors A

{

and C of one LPRM string in the center of the core should be monitored.

l LIMERICK - UNIT 1 3/4 4-la Amendment No. 30 t

x j

..... ~.

REACTOR COOLANT SYSTEM RECIRCUU6 TION PUMPS LIMITING CONDITION FOR OPERATION l

3.4.1.3 Recirculation loop flow mismatch shall be maintained within:

l 5% of each other with core flow greater than or equal to 70% of

]

a.

rated core flow, b.

10% of each other with core flow less than 70% of rated core flow.

APPLICABILITY:

OPERATIONAL CONDITIONS 1* and 2* during two recirculation loop i

operation.

ACTION:

With the recirculation loop flows different by more than the specified l

limits, either:

Reitore the recirculation loop flows to within the specified limit -

a.

within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or b.

Shttdown one of the recirculation loops within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ar take the ACTION required by Specification 3.4.1.1.

i 4

1 SURVEILLANCE I! REQUIREMENTS 1

4.4.1.3 Recirculation loop flow mismatch shall be verified to be within the l

limits at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

See Special Test Exception 3.10.4.

1 l

l I

LIMERICK - UNIT 1 3/4 4-5 Amendment No.30 l

4

2 i

l REACTOR C0OLANT SYSTD4 IDLERECIRCULATIONLOOPSTARTUP LIMITING CONDITION FOR OPERATION 4

3.4.1.4 An idle recirculation loop shall not be started unless the temperature dif ferential between the reactor pressure vessel steam space coolant and the bottom head drain line coolant is less than or equal to 145'F, and:

a.

When both loops have been idle, unless the temperature differential between the reactor coolant within the idle loop to be started up and the coolant in the reactor pressure vessel is less than or equal to 50'F, or b.

When only one loop has been idle, unless the temperature differential

~

between the reactor coolant within the idle and operating recircula-tion loops is less than or equal to 50'F and the operating loop l

flow rate is less than or equal to 50% of rated loop flow.

l APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, 3, and 4.

ACTION:

With temperature differences and/or flow rates exceeding the above limits.

l suspend startup of any idle recirculation loop.

l SURVEILLANCE REQUIREMENTS l

4.4.1.4 The temperature differentials and flow rate shall be determined to be within the limits w1 thin 15 minutes prior to startup of an idle recirculation loop.

1 LIMERICK - UNIT 1 3/4 4-6

g 4

l I,

LIFT INTENTIONALLY SLANK LIERICK - Um!T 1 8 3/4 2-3 Amendment No.7 M s q, i

- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ - _ _ - _ = - _

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POWER DISTRIBUTION LIMITS BASESL a

i 3/4.2.3-' MINIMUM CRITICAL POWER RATIO l

~!

i The required operating limit MCPRs at steady-state operating conditions-l as specified in Specification ~3.2.3 are derived from the established fuel i

cladding: integrity Safety Limit-MCPR, and an analysis offabnormal operational.

I transients.

For any abnormal operating transient analysis evaluation with the l

initial condition of the reactor being at the' steady-state' operating limit, it-is required that' the resulting MCPR does not decrease below the Safety Limit

^j

, MCPR at any time during the transient assuming instrument trip setting'given

,in Specification.2.2.'

.To assure that the fuel cladding integrity Safety Limit is not exceeded I

during any anticipated abnormal operational teansient,'the most limiting tran-sients have been analyzed to determine which Tesult.in the largest reduction in CRITICAL POWER RATIO (CPR).

The type of transients evaluated were loss of i

~

flow, increase in. pressure and power, positive reactivity insertion, and d

coolant temperature decrease.

i

~ The evaluation of a given transient begins with the system initial para.

1 meters shown in FSAR Table 15.0-2 that are input to a GE-core dynamic behavior.

l transient computer program.

The codes used to evaluate transients are discussed in Reference 2.

The purpose of the K, factor of Figure 3.2.3-2.is to ' define operating limits at other than rated core flow conditions.

At less than 100% of rated q

flow the required MCPR is the product of the MCPR and the K[ed dur factor.

The K factors assure that the Safety Limit MCPR will not be viola l

i increase transient resulting from a motor generator speed control failure.

l The K factors may be applied to both manual and automatic flow control modes.

f J

The K, factors values shown in Figure 3.2.3-2 were developed generically and are ap#1icable to all BWR/2, BWR/3, and BWR/4 reactors.

The K factors were f

derived using the flow control line corresponding to RATED THERMAL POWER at rated core flow.

For the manual flow control mode, the K factors were calculated such that f

for the maximum flow rate, as limited by the pump scoop tube set point and the corresponding THERMAL POWER along the rated flow control line, the lirt.iting bundle's relative power was adjusted until the MCPR changes with different core flows.

The ratio of the MCPR calculated at a given point of core flow, divided by the operating limit MCPR, determines the K.

7 l

I LIMERICK - UNIT 1 B 3/4 2-4 Amendment No. 7, If, 30 l

---_______________________J

ML20248E562

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