ML20141C928

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Proposed Tech Specs Re Recirculation Sys W/One & Two Loop Operation,Supporting Operation W/One Recirculation Loop Out of Svc
ML20141C928
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 03/27/1986
From:
PENNSYLVANIA POWER & LIGHT CO.
To:
Shared Package
ML18040A803 List:
References
NUDOCS 8604070347
Download: ML20141C928 (8)
v • d • e


Text

. .

. L 3/4.4 REACTOR COOLANT SYSTEM

!T 3/4.4.1 RECIRCULATION SYSTEM RECIRCULATION LOOPS - Two LcoP OPERAnod LIMITING CONDITION FOR OPERATION 3.4.1.1.1 Two reactor coolant system recirculation loops shall be in operation.

je and:

a. Total core flow shall be greater than or equal to 45 million.lbs/hr,,or
b. THERMAL POWER shall be less than or equal to the limit specified in Figure 3. + l . 8 . l - 1.

APPLICABILITY:_ ' OPERATIONAL CONDITIONS 1* and 2*f', emf + Arb s 5 8 I"r **" #

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ACTION:

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x With one reactor coolant system recirculation loop not in operation,4

' r :dfrtet '-it'-t: tr rd: rig :f r ti;. ;' "" 1 = i.v b. .

the er pr'. t; th: li..it : ni'ic '"6s 3.t.1.1-1, rd be in at least HOT SHUT 00WN "- +" -+ " "

b. With no reactor coolant system recirculation loops in operation,

.ip immediately initiate an orderly reduction of THERMAL POWER to less Wi than or equal to the limit specified in Figure 0 h measures to place the unit in at least STARTUPfw.t.1.11, HOT SHUTDOWN within the next 6^ hours.

ithin 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in and initia 2.4.t.1 / -1 C.' c.

With two reactor coolant, system recirculation loops in operation and total core flow less than 45 million lbs/hr and THERMAL POWER greater than the limit specified in Figure 2. 0.1.1 { ,,g,f,,,t.f

1. Reduce THERMAL POWER to less than or equal to the limit specified in Figure 2.t.1.1-1 or 3 ,,, ,, ,, , , f .

g 2. Increase core flow to greater than 45 million lbs/hr, or

[g@ 3. Determine the APRM and LPRM*** neutron flux noise levels within o8 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and: .

on 50 '

a) If the APRM and LPRM*** neutron flux noise levels are less y than three' times their established baseline levels, continue

~

' no to determine the noise levels at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and R within 30 minutes after the completion of a THERMAL POWER S@

ox increase o.f at least 5% of RATED THERMAL POWER, or So

      • b) If the APRii or LPRM*** neutron flux noise levels are greater

, than or equal to three times their established baseline i levels, immediately initiate corrective action and restore j the noise levels to within the required limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> h

by increasing core flow to greater than 45 million'lbs/hr, and/or by initiating an~ orderly reduction of THERMAL POWER to less than or equal to the limit specified in Figureg. 0.1.F..

I_ ' "

3.9.t.I.1-1

  • See Special Test Exception 3.10.4. .
    • " Detectors A and C of one LPRM string per. core octant plus detectors A ano C of one LPRM string in the' center of the core should. be monitored.
  1. Su. Sy sE.Gauk 3.4.t.t.1 for shic /*y yvsh% reguo%eds. -

REACTOR COOLANT SYSTEM RECIRCULATION LOOPS - SINGLE LOOP OPERATION LIMITING CONDITION FOR OPERATION

, c 3.4.1.1.2 One reactor coolant recirculation loop shall be in operation with the pump speed 6 80% of the rated pump speed, and

a. the following revised specification limits shall be followed:
1. Specification 2.1.2: the MCPR Safety Limit shall be increased to 1.07.
2. Table 2.2.1-1: the APRM Flow-Biased Scram Trip Setpoints shall be as follows:

Trip Setpoint Allowable Value 10.58W + 55% dE0.58W + 58%.

3. Specification 3.2.1: the MAPLHGR limits shall be as follows:
a. GE fuel: the limits specified in Figures 3.2.1-1 and 3.2.1-2, multiplied by 0.81.
b. Exxon fuel: the limits specified in Figure 3.2.1-2 multiplied by 0.81.
4. Specification 3.2.2: the APRM Setpoints shall be as follows:

Trip Setpoint Allowable Value S d (0.58W + 55%)T S 4 (0.58W + 58%)T SRB.d (0.58W + 46%)T S

gg es(0.58W + 49%)T

5. Table 3.3.6-2: the RBM/APRM Control Rod Block Setpoints shall be as follows:
a. RBM - Upscale Trip Setpoint Allowable Value
1. gL0.66W + 35% dEO.66W + 38%
2. 6 0.66W + 37% $ 0.66W + 40%

, 5.a.1 and 5.a.2 shall be used in conjunction with the MCPR limits specified in Figures 3.2.3-la and 3.2.3-1b, gespectively.

b. APRM-Flow Biased Trip Setpoint Allowable Value 20.58W + 46% 2 0.58W + 49%
b. APRM and LPRM*** neutron flux noise levels shall be less than three times their established baseline levels when THERMAL POWER !s greater than the limit specified in Figure 3/4.1.1.1-1.

APPLICABILITY: OPERATIONAL CONDITIONS 1* and 2*, except during two loop operation.f

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ACTION:

a. With no reactor coolant system recirculation loops in operation, take the ACTION required by Specification 3.4.1.1.1.
b. With any of the limits specified in 3.4.1.1.2a not satisfied, take the ACTION required by the referenced Specification.

W c. With the APRM or LPRM*** neutron flux noise levels greater than WCfb or equal to three times their established baseline icvels when Igf6 THERMAL POWER is greater than the limit specified in Figure 3/4.1.1.1-1, immediately initiate corrective action and restore the noise levels to within the required limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> by initiating an orderly reduction of THERMAL POWER to less than or equal to the limit specified in Figure 3.4.1.1.1-1. Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />,

d. With one or more jet pumps inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.4.1.1.2.1 Upon entering single loop operation and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter, verify that the pump speed in the operating loop is f.80% of the rated pump speed.

4.4.1.1.2.2 With THERMAL POWER greater than the limit specified in Figure 3.4.1.1.1-1, determine the APRM and LPRit*** neutron flux noise levels within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Continue to determine the noise levels at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and within 30 minutes after the completion of a THERMAL POWER increase R 5% of RATED THERMAL POWER.

4.4.1.1.2.3 Within 15 minutes prior to either THERMAL POWER increase resulting from a control rod withdrawal or recirculation loop flow increase, verify that the following differential temperature requirements are met if THERMAL POWER is 6 30%****

of RATED THERMAL POWER or the recirculation loop flow in the operating recirculation loop is d 50%**** of rated loop flow:

a. W 145*F between reactor vessel steam space coolant and bottom head drain line coolant, b.fff 50'F between the reactor coolant within the loop not in operation and the coolant in the reactor pressure vessel, and c.ffn50'F between the reactor coolant within the loop not in operation and operating loop.

4.4.1.1.2.4 a. Establis't a baseline APRM and LPRM neutron flux noise value at a point within 5% RATED THERMAL POWER of the 100% rated

l IMELTs 3/4.4.1.1.1 (Delete former ACTION a; replace with the following:)

ACTION:

a. With one reactor coolaht system recirculation loop not in operation, comply with the requirements of Specification 3/4.1.1.2 or take the associated ACTION.

3/4.4.1.1.2 (Delete proposed ACTION b; replace with the following:)

b. With any of the limits specified in 3/4.1.1.2a not satisfied:

8 1. Upon entering single loop operation comply with the new limits within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

2. If the provisions of ACTION b.1 do not apply, take the ACTION (s) required by the referenced Specification (s).

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3/a.4 REACTOR COOLANT SYSTEM

'3/c.4.1 RECIRCULATION SYSTEM RECID.CULATION LOOPS' - Tuo L..r onu n.4 LIMITING CONDITION FOR OPERATION 3.4.1.1.1Two and:

reactor coolant system recirculation loops shall be in operation.

a.

Total or core flow shall be greater than or equal to 45 million 1bs/hr, b.

THERMAL POWER shall be less than or equal to the limit specified in Figure 2 . 0. 1 . 1 1. 3 . 4 . l.a.i - 1 APPLICABILITY:

TION: "*

OPERATIONAL CONDITIONS 1* and 2*Me.uyt J r.h ,.yle

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l l a. With one reecT.or coolant system recirculaticn loop not in operation, + l

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at least HOT SHUTOOWN, ;C. -

. . . , . d. 1 . . . . . /

b. With no reactor coolant system recirculation loops in operation, g immediately initiate an orderly reduction of THERMAL POWER to less 7 than or equal to the limit specified in Figure 2.t.1.11, and initiata d u f /Als M r" measures to place the unit in at least STARTUP within d 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. ' 3.<v.s.,. t- f
c. With two reactor coolant system recirculation loops in cgc-ation and total core flow less than 45 million 1bs/hr and THERMAL P0ki greater than the limit specified in Figure :. ". ..; 1:
1. 3. 4{. t.4.f
  • Reduce THERMAL POWER to less than or equa/l to the limit specified in Figure 2." 1.1 ', or
2. Increase cora flow to greater than 45'million,1bs/hr, or 2.

Determine 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and: the APRM and LPRM*** neutron flux noise levels within a) If the APRM and LPRM*** neutron' flux noise levels are less than three times their established baseline levels, continue to determine the noise levels at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and within 30 minutes after the comoletion of a THERMAL POWER increase of at least 5% of RATED THERMAL P0.WER, or b) ,If the APRM cr LPRMa** neutron flux noise levels are greater

'than or equal to three times their established baseline levels, immediately initiate corrective action and restore the noise levels to within the required limits within 2 hcurs' by increasing core flow to greater than 45 million 1bs/hr.

and/cr by initiating an orderly reduction of THERMAL POWER '

to less than or equal to the limit specified in Figure

  • ' i.1 '-.

3.<l.t.t.t-I

  • See 5pecial Test Exception 3.10.4 "r* Detectors 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.

p If b S eeWesk.1.4. I.I.2 .[,,s,ge.I.or o pes.L regu.ie w , .

FUSQUEHANNA - UM T 2 3/.s 4-1 Am'endment No.2

REACTOR COOLANT SYSTEM RECIRCULATION LOOPS - SINGLE LOOP OPERATION LIMITING CONDITION FOR OPERATION 3.4.1.1.2 One reactor coolant recirculation loop shall be in operation with the pump speed 6.90% of the rated pump speed, and

a. the following revised specification limits shall be follovad:
1. Specification 2.1.2: the MCPR Safety Limit shall be increased to 1.07.
2. Table 2.2.1-1: the APRM Flow-Biased Scram Trip Setpoints shall be as follows:

Trip Setpoint Allowable Value S 0.58W + 55% A0.58W + 58%.

3. Specification 3.2.1: the MAPLHCR limits shall be the limits specified in Figures 3.2.1-1, 3.2.1-2, and 3.2.1-3, multiplied by 0.81.
4. Specification 3.2.2: the APRM Setpoints shall be as follows:

Trip Setpoint Allowable Value S f (0.58W + 55%)T S * (0.58W + 58%)T S

RB 4(0.58W + 46 M SRBd (0.58W + 49%)T

5. Table 3.3.6-2: the RBM/APRM Control Rod Block Setpoints shall be as follows:
a. RBM - Upscale Trip Setpoint Allowable Value
1. A0.66W + 35% $0.66W + 38%
2. 20.66W + 37% $0.66W + 40%

5.a.1 and 5.a.2 shall be used in conjunction with the MCPR limits specified in Figures 3.2.3-la and 3.2.3-lb, respectively.

b. APRM-Flow Biased Trip Setpoint Allowable Value 60.58W + 46% $0.58W + 49%
b. APRM and LPRM*** neutron flux noise levels shall be less than three times their established baseline levels when THERMAL POWER is greatair than the limit specified in Figure 3/4.1.1.1-1.

APPLICABILITY: OPERATIONAL CONDITIONS 1* and 2*, except during two loop operation.#

ACTION:

a. With no reactor coolant system recirculation loops in operation, take the ACTION required by Specification 3.4.1.1.1.

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b. With any of the limits specified in 3.4.1.1.2a not satisfied, take the ACTION required by the referenced Specification,
c. With the APRM or LPRM*** neutron flux noise levels greater than 4 or equal to three times their established baseline levels when THERMAL POWER is greater than the limit specified in Figure Qg1LT 3/4.1.1.1-1, immediately initiate corrective action and restore the noise levels to within the required limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> by initiating an orderly reduction of THERMAL POWER to less than or equal to the limit specified in Figure 3. 4 .1.1.1- 1. Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
d. With one or more jet pumps inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCE REQUIREMENTS _ __

4.4.1.1.2.1 Upon entering single loop operation and at least once per 2<.

hours thereafter, verify that the pump speed in the operating loop is d.90% of the rated pump speed.

4.4.1.1.2.2 With THERMAL POWER greater than the limit specified in Figure 3.4.1.1.1-1, determine the APRM and LPRM*** neutron flux noise levels within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Continue to determine the noise levels at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and within 30 minutes after the completion of a THERMAL POWER increase f 5% of RATED THERMAL POWER.

4.4.1.1.2.3 Within 15 minutes prior to either THERMAL POWER increase resulting from a control rod withdrawal or recirculation loop flow increase, verify that the following differential temperature requirements are met if THERMAL POWER is n 30%****

of RATED THERMAL POWER or the recirculation loop flow in the operating' recirculation loop is $ 50%**** of rated loop flow:

a. f145'F between reactor vessel steam space coolant and bottom head drain line coolant, b.ff f50*F between ths reactor coolant within the loop not in operation and tFe coolant in the reactor pressure vessel, and c.fi f50*F between the reactor coolant within the loop not in operation and operating loop.

4.4.1.1.2.4 a. Establish a baseline APRM and LPRM neutron flux noise value at a point within 5% RATED THERMAL POWER of the 100% rated

' rod line with total core flow between 35% and 50% of rated total core flow during startup testing following each refueling outage, or

O 14eas 3/4.4.1.1.1 (Delete former ACTION a; replace with the following:)

ACTION:

@ a. With one reactor coolaht system recirculation loop not in operation, comply with the requirements of Specification 3/4.1.1.2 or take the associated ACTION.

3/4.4.1.1.2 (Delete proposed ACTION b; replace with the following:)

b. With any of the limits specified in 3/4.1.1.2a not satisfied:

8 1. Upon entering single loop operation, comply with the new limits within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

2. If the provisions of ACTION b.1 do not apply, take the ACTION (s) required by the referenced Specification (s).

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