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{{#Wiki_filter:TECHNICAL SPECIFICATION MARKUPS 9304090264 930402 p f PDR ADOCK 05000387 PDR R IR LATI NL P.-IN LEL P PERAT N LIMITIN NDITION F R OPERATION 3.4.1~1.2 One reactor coolant recirculation loop shall be in operation with the pump speed s 80%of the rated pump speed and the reactor at a THERMAL POWER/core flow condition outside of Regions I and II of Figure 3.4.1.1.1-1, and a.the following revised specification limits shall be followed: 1.Specification 2.1.2: the MCPR Safety Limit shall be increased to 1.07.4.0 V~E 2.Table 2.2.1-1: the APRM Flow-Biased Scram Trip Setpoints shall be as follows: '''=~,;-Trip',Setpoint.~;~"."";-.>-."'P~~~Pr-".'gj".;~~~'4b:.':'"lAIIowabhi:Value
{{#Wiki_filter:TECHNICAL SPECIFICATION MARKUPS 9304090264 930402 05000387 PDR ADOCK f p PDR
~-,":,~'",'.
 
s 0.58W+54%s 0.58W+57%v 0 0 H~v CTj\3.Specification 3.2.2: the APRM Setpoints shall be as follows: """"j~'":"'":""')Trip,'Setpoht~"-""'~"""'i".
R   IR   LATI NL       P.     - IN LEL             P     PERAT         N LIMITIN     NDITION F         R OPERATION 3.4.1 1.2 One reactor coolant recirculation loop shall be in operation with the pump speed
"'F~': '~4''Z~~'-:"AIIowable'Yah'-';;<i+:.--'"i>>
                ~
S s (0.58W+54%)T Sp s (0.58W+45%)T S s (0.58W+57%)T S<s (0.58W+48%)T 4.Specification 3.2.3: The MINIMUM CRITICAL POWER RATIO (MCPR)shall be greater than or equal to the largest of the following values: I a.the MCPR determined from Figure 3.2.3-1 plus 0.01, and I b.the MCPR determined from Figure 3.2.3-2, Figure 3.2.3-3, or Figure 3.2.3-4, as appropriate, plus 0.01.~~~~~g.'g Table 3.3.6-2: the RBM/APRM Control Rod Block Setpoints shall be as follows: a.RBM-Upscale b.APRM-Flow Biased Trip Setpoint:.
s 80% of the rated pump speed and the reactor at a THERMALPOWER/core flow condition outside of Regions I and II of Figure 3.4.1.1.1-1, and
-,', s 0.66W+36%Trip Setpoint'..=".~-'0.58W+45%~v.",;.'Allowable Valoe:.'".'-':.'
: a. the following revised specification limits shall be followed:
0.66W+39%;.'-.';-'+;:AIIowibie Vetue~,",',,"'
: 1. Specification 2.1.2: the MCPR Safety Limit shall be increased to 1.07.
s 0.58W+48%*:<<<<''+.d operation.&#xb9; SUSQUEHANNA
: 2. Table 2.2.1-1: the APRM Flow-Biased Scram Trip Setpoints shall be as follows:
-UNIT 1 3/4 4-1c Amendment No.118  
4.
0 V
                                '
~E                                  ''=~,;- Trip',Setpoint.~;~"."";-.>-."'P~~~Pr-" .'gj".;~~~'4b:.':'"lAIIowabhi:Value ~-,":,~'",'.
s 0.58W + 54%                                             s     0.58W + 57%
: 3. Specification 3.2.2: the APRM Setpoints shall be as follows:
v 0
                              """"j~'":"'":""')Trip,'Setpoht~"-""'~"""'i". "'F~':       '~4'' Z~~'-:"AIIowable'Yah'-';;<i+:.--'"i>>
0 S s     (0.58W+ 54%) T                                         S s       (0.58W + 57%) T H
Sp      s (0.58W + 45%) T                                       S<       s   (0.58W + 48%) T
      ~ v
: 4. Specification 3.2.3: The MINIMUMCRITICALPOWER RATIO (MCPR) shall be greater than or equal to the largest of the following values:
I
: a. the MCPR determined from Figure 3.2.3-1 plus 0.01, and                                                           I
: b. the MCPR determined from Figure 3.2.3-2, Figure 3.2.3-3, or Figure 3.2.3-4, as appropriate, plus 0.01.
                                  ~   ~                                         ~     ~
CTj              g.'g   Table 3.3.6-2: the RBM/APRM Control Rod Block Setpoints shall be as
                                          ~
follows:
\
                                                                                                                                  ~ v.
Trip Setpoint:. -,           ',   ",;. 'Allowable Valoe:.'".'-':.'
: a. RBM- Upscale                    s  0.66W + 36%                                  0.66W + 39%
Trip Setpoint      '..=". ~ -' ;.'-.';-'+;:AIIowibie Vetue~,",',,"'
                  *: <<       b. APRM- Flow Biased operation.&#xb9;
                                                                <<
0.58W + 45%
                                                                                '               '+.
s    0.58W + 48%
d SUSQUEHANNA - UNIT 1                                   3/4 4-1c                                           Amendment No. 118
 
RESPONSE TO NRC QUESTIONS REV. 1 RESPONSE TO NRC QUESTIONS REACTOR  SYSTH6  BRANCH QUESTION 3 If  single loop operation (SLO) yields a higher peak cladding temperature (PCT) than two loop operation, why is the upper bound peak cladding temperature (UBPCT) based on two loop operation applicable for SLO? Does the limiting single failure and break size remain the same for SLO as for two loop operation? Discuss the applicability of SAFER/GESTR for SLO in view of the fact SLO results in a higher PCT.
Operation with one recirculation loop out of service is allowed, but        it is not considered a normal mode of operation. SLO is a special operational condition when only one of the two recirculation loops is operable. In this operating condition, the reactor power will be limited to less than 804 of rated by the maximum achievable core flow, which is typically less than 604 of rated core flow. A postulated LOCA occurring in the active recirculation loop during SLO would cause a more rapid coastdown,of the recirculation flow than would occur in two loop operation, where one active loop would remain intact. This rapid coastdown causes an earlier boiling transition time and deeper penetration of boiling transition into the bundle, which tends to increase the calculated PCT. However, the PCT effects of the early boiling transition are substantially offset by the mitigating effect of the lower power level achievable at the start of such an event. The SAFER/GESTR-LOCA    analysis results for Susquehanna    (NEDC-32071P) for  SLO and two  loop operation are well below 2200'F.
The ECCS performance    for Susquehanna under SLO was evaluated using SAFER/GESTR-LOCA. Calculations for the DBA were performed using both nominal and Appendix K inputs. The SLO SAFER/GESTR-LOCA analysis for the DBA assumes that there is essentially no period of recirculation pump coastdown. Thus, dryout is assumed to occur simultaneously at all axial locations of the hot bundle shortly after initiation of the event. Dryout is assumed to occur in one second for the nominal case and O.l second for the Appendix K case.        These assumptions are very conservative and provide bounding results for the DBA under SLO.
The  two-loop Appendix K break spectrum documented in NEDC-32071P is representative of SLO because the two-loop spectrum was analyzed assuming a one second dryout time for all axial locations of the hot bundle. As shown by the two-loop break spectrum, the DBA is the limiting case for SLO. In addition, SLO will affect the DBA results more than the smaller breaks.        With breaks smaller than the DBA, there is a longer period of nucleate and/or film boiling prior to fuel uncovery to remove the fuel stored energy.
An LHGR reduction (multiplier) of 0.70 will be imposed when the plant is in SLO. As shown in Table 5-6 of NEDC-32701P, the SLO results are less limiting  (i.e.,  lower PCTs) than the results for the two loop DBA LOCA.
Thus, the  licensing  PCT  is  based appropriately  on two loop operation rather than SLO.


RESPONSE TO NRC QUESTIONS RESPONSE TO NRC QUESTIONS REACTOR SYSTH6 BRANCH REV.1 QUESTION 3 If single loop operation (SLO)yields a higher peak cladding temperature (PCT)than two loop operation, why is the upper bound peak cladding temperature (UBPCT)based on two loop operation applicable for SLO?Does the limiting single failure and break size remain the same for SLO as for two loop operation?
Discuss the applicability of SAFER/GESTR for SLO in view of the fact SLO results in a higher PCT.Operation with one recirculation loop out of service is allowed, but it is not considered a normal mode of operation.
SLO is a special operational condition when only one of the two recirculation loops is operable.In this operating condition, the reactor power will be limited to less than 804 of rated by the maximum achievable core flow, which is typically less than 604 of rated core flow.A postulated LOCA occurring in the active recirculation loop during SLO would cause a more rapid coastdown,of the recirculation flow than would occur in two loop operation, where one active loop would remain intact.This rapid coastdown causes an earlier boiling transition time and deeper penetration of boiling transition into the bundle, which tends to increase the calculated PCT.However, the PCT effects of the early boiling transition are substantially offset by the mitigating effect of the lower power level achievable at the start of such an event.The SAFER/GESTR-LOCA analysis results for Susquehanna (NEDC-32071P) for SLO and two loop operation are well below 2200'F.The ECCS performance for Susquehanna under SLO was evaluated using SAFER/GESTR-LOCA.
Calculations for the DBA were performed using both nominal and Appendix K inputs.The SLO SAFER/GESTR-LOCA analysis for the DBA assumes that there is essentially no period of recirculation pump coastdown.
Thus, dryout is assumed to occur simultaneously at all axial locations of the hot bundle shortly after initiation of the event.Dryout is assumed to occur in one second for the nominal case and O.l second for the Appendix K case.These assumptions are very conservative and provide bounding results for the DBA under SLO.The two-loop Appendix K break spectrum documented in NEDC-32071P is representative of SLO because the two-loop spectrum was analyzed assuming a one second dryout time for all axial locations of the hot bundle.As shown by the two-loop break spectrum, the DBA is the limiting case for SLO.In addition, SLO will affect the DBA results more than the smaller breaks.With breaks smaller than the DBA, there is a longer period of nucleate and/or film boiling prior to fuel uncovery to remove the fuel stored energy.An LHGR reduction (multiplier) of 0.70 will be imposed when the plant is in SLO.As shown in Table 5-6 of NEDC-32701P, the SLO results are less limiting (i.e., lower PCTs)than the results for the two loop DBA LOCA.Thus, the licensing PCT is based appropriately on two loop operation rather than SLO.
~'
~'
O Errata and Addenda Sheet Applicable to: Publication No.Title Units 1 and 2 SAFER GESTR-LOCA Loss-Of-Co lant Accident Anal sis Issue Date Gf'Nvdeer fnerJry/15 Curler A@eve San Jm.CA 85125 EBA No.Date c 199 Note: Correct all copies of the applicable publication as specified below.References (Secdaa Pape Pareyapt CkeJ lmtrecdaer (Conec0ies aif Adkera)Pages 5-6 and 5-7 Replace with new pages 5-6 and 5-7 Page 5-l3 Replace with new Page 5-13 (change brackets in right hand margin indicate areas where report has been changed)  
O                                               Errata and Addenda Sheet Gf'Nvdeer fnerJry
                                                /15 Curler A@eve San Jm. CA 85125 Applicable to:
Publication No.                                EBA No.
Title                                          Date                 c 199 Units  1 and 2 SAFER GESTR-LOCA  Loss-Of-      Note: Correct       all copies of the Co  lant Accident Anal sis                              applicable publication as Issue Date                                              specified below.
References                               lmtrecdaer (Secdaa Pape                       (Conec0ies aifAdkera)
Pareyapt CkeJ Pages   5-6 and 5-7 Replace with new pages         5-6 and 5-7 Page   5-l3         Replace with new Page 5-13 (change brackets in right hand margin           indicate areas where report has been changed)
 
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Revision as of 02:20, 30 October 2019

Proposed TS 3.4.1.1.2 Re LCO for Recirculation Loops,Single Loop Operation
ML17157C274
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 04/02/1993
From:
PENNSYLVANIA POWER & LIGHT CO.
To:
Shared Package
ML17157C275 List:
References
NUDOCS 9304090264
Download: ML17157C274 (8)
v • d • e


Text

TECHNICAL SPECIFICATION MARKUPS 9304090264 930402 05000387 PDR ADOCK f p PDR

R IR LATI NL P. - IN LEL P PERAT N LIMITIN NDITION F R OPERATION 3.4.1 1.2 One reactor coolant recirculation loop shall be in operation with the pump speed

~

s 80% of the rated pump speed and the reactor at a THERMALPOWER/core flow condition outside of Regions I and II of Figure 3.4.1.1.1-1, 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:

4.

0 V

'

~E =~,;- Trip',Setpoint.~;~"."";-.>-."'P~~~Pr-" .'gj".;~~~'4b:.':'"lAIIowabhi:Value ~-,":,~'",'.

s 0.58W + 54% s 0.58W + 57%

3. Specification 3.2.2: the APRM Setpoints shall be as follows:

v 0

""""j~'":"'":""')Trip,'Setpoht~"-""'~"""'i". "'F~': '~4 Z~~'-:"AIIowable'Yah'-';;<i+:.--'"i>>

0 S s (0.58W+ 54%) T S s (0.58W + 57%) T H

Sp s (0.58W + 45%) T S< s (0.58W + 48%) T

~ v

4. Specification 3.2.3: The MINIMUMCRITICALPOWER RATIO (MCPR) shall be greater than or equal to the largest of the following values:

I

a. the MCPR determined from Figure 3.2.3-1 plus 0.01, and I
b. the MCPR determined from Figure 3.2.3-2, Figure 3.2.3-3, or Figure 3.2.3-4, as appropriate, plus 0.01.

~ ~ ~ ~

CTj g.'g Table 3.3.6-2: the RBM/APRM Control Rod Block Setpoints shall be as

~

follows:

\

~ v.

Trip Setpoint:. -, ', ",;. 'Allowable Valoe:.'".'-':.'

a. RBM- Upscale s 0.66W + 36% 0.66W + 39%

Trip Setpoint '..=". ~ -' ;.'-.';-'+;:AIIowibie Vetue~,",',,"'

  • << b. APRM- Flow Biased operation.¹

<<

0.58W + 45%

' '+.

s 0.58W + 48%

d SUSQUEHANNA - UNIT 1 3/4 4-1c Amendment No. 118

RESPONSE TO NRC QUESTIONS REV. 1 RESPONSE TO NRC QUESTIONS REACTOR SYSTH6 BRANCH QUESTION 3 If single loop operation (SLO) yields a higher peak cladding temperature (PCT) than two loop operation, why is the upper bound peak cladding temperature (UBPCT) based on two loop operation applicable for SLO? Does the limiting single failure and break size remain the same for SLO as for two loop operation? Discuss the applicability of SAFER/GESTR for SLO in view of the fact SLO results in a higher PCT.

Operation with one recirculation loop out of service is allowed, but it is not considered a normal mode of operation. SLO is a special operational condition when only one of the two recirculation loops is operable. In this operating condition, the reactor power will be limited to less than 804 of rated by the maximum achievable core flow, which is typically less than 604 of rated core flow. A postulated LOCA occurring in the active recirculation loop during SLO would cause a more rapid coastdown,of the recirculation flow than would occur in two loop operation, where one active loop would remain intact. This rapid coastdown causes an earlier boiling transition time and deeper penetration of boiling transition into the bundle, which tends to increase the calculated PCT. However, the PCT effects of the early boiling transition are substantially offset by the mitigating effect of the lower power level achievable at the start of such an event. The SAFER/GESTR-LOCA analysis results for Susquehanna (NEDC-32071P) for SLO and two loop operation are well below 2200'F.

The ECCS performance for Susquehanna under SLO was evaluated using SAFER/GESTR-LOCA. Calculations for the DBA were performed using both nominal and Appendix K inputs. The SLO SAFER/GESTR-LOCA analysis for the DBA assumes that there is essentially no period of recirculation pump coastdown. Thus, dryout is assumed to occur simultaneously at all axial locations of the hot bundle shortly after initiation of the event. Dryout is assumed to occur in one second for the nominal case and O.l second for the Appendix K case. These assumptions are very conservative and provide bounding results for the DBA under SLO.

The two-loop Appendix K break spectrum documented in NEDC-32071P is representative of SLO because the two-loop spectrum was analyzed assuming a one second dryout time for all axial locations of the hot bundle. As shown by the two-loop break spectrum, the DBA is the limiting case for SLO. In addition, SLO will affect the DBA results more than the smaller breaks. With breaks smaller than the DBA, there is a longer period of nucleate and/or film boiling prior to fuel uncovery to remove the fuel stored energy.

An LHGR reduction (multiplier) of 0.70 will be imposed when the plant is in SLO. As shown in Table 5-6 of NEDC-32701P, the SLO results are less limiting (i.e., lower PCTs) than the results for the two loop DBA LOCA.

Thus, the licensing PCT is based appropriately on two loop operation rather than SLO.

~'

O Errata and Addenda Sheet Gf'Nvdeer fnerJry

/15 Curler A@eve San Jm. CA 85125 Applicable to:

Publication No. EBA No.

Title Date c 199 Units 1 and 2 SAFER GESTR-LOCA Loss-Of- Note: Correct all copies of the Co lant Accident Anal sis applicable publication as Issue Date specified below.

References lmtrecdaer (Secdaa Pape (Conec0ies aifAdkera)

Pareyapt CkeJ Pages 5-6 and 5-7 Replace with new pages 5-6 and 5-7 Page 5-l3 Replace with new Page 5-13 (change brackets in right hand margin indicate areas where report has been changed)

/>

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