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{{#Wiki_filter:Attachment   II Marked Up Copy of R.E. Ginna Nuclear Power Plant Technical Specifications Included Pages:
{{#Wiki_filter:Attachment II Marked Up Copy ofR.E. Ginna Nuclear Power Plant Technical Specifications Included Pages:
3.3-26 B 3.3-82*
3.3-26 B 3.3-82*
      , B 3.3-84" These bases pages are being provided for information only to show the changes RG8cE intends to make following NRC approval of the I.AR. The bases are under RGB control for all changes in accordance with Specification 5.5.13.
, B 3.3-84" These bases pages are being provided for information only to show the changes RG8cE intends to make followingNRC approval ofthe I.AR. The bases are under RGB control for all changes in accordance with Specification 5.5.13.
9710020027 970929 PDR     ADQCK 05000244 P                       PDR
9710020027 970929 PDR ADQCK 05000244 P
PDR


ESFAS   Instrumentation 3.3.2 Table 3.3   '-1   (page 2 of 3)
ESFAS Instrumentation 3.3.2 Table 3.3 '-1 (page 2 of 3)
Engineered safety Feature Actuation system Instrwlentation APPLICABLE MODES OR OTHER SPECIFIED     REQUIRED                       SURVEILLANCE   ALLOMABLE            TRIP FUNCTION              CONDITIONS      CHANNELS         CONDITIONS   REQUIREMENTS       VALUE       SETPOINT
Engineered safety Feature Actuation system Instrwlentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED SURVEILLANCE CHANNELS CONDITIONS REQUIREMENTS ALLOMABLE VALUE TRIP SETPOINT
: 4. Steam Line Isolation
: 4. Steam Line Isolation
: a. Manual   Initiation           (b) 3(b)     1   per            D,G      SR  3.3.2.4                          NA loop
: a. Manual Initiation
: b. Automatic Actuation        1   2(b) 3(b)   2 trains           E,G       SR 3.3.2 '                           NA Logic and Actuation Relays
: b. Automatic Actuation Logic and Actuation Relays
: c. Contaiment Pressure -High High          2(b) 3(b)                        -F,G      SR 3.3.2.1     s 20   psig 1
: c. Contaiment Pressure -High High (b) 3(b) 1 2(b) 3(b) 1 2(b) 3(b) 1 per loop 2 trains D,G E,G
RR 3.3.2.2                     (C.RR-I 3.3.2.5 s~
-F,G SR 3.3.2.4 SR 3.3.2 '
SR 0.I (=.(
SR 3.3.2.1 s 20 psig RR 3.3.2.2 SR 3.3.2.5 NA NA (C.RR-I
: d. High Steam Flow 1   2(b) 3(b)     2   per           F,G       SR 3.3.2.1                       s 0.4E6
: d. High Steam Flow 1 2(b) 3(b) 2 per
                                    ~    ~
~
steam                        SR 3.3.2.2     ibm/hr 9        ibm/hr    oI line                        SR 3.3.2.5       i%i-ps+       ~vpsl g IOUS Pr        I OOS Coincident with               Refer to Function     1 (Safety Injection) for   all Safety Injection                  initiation functions       and requirements.
~
Coincident with           122       3       2   per           F,G       SR 3.3.2.1       a 543   F     a 545  F T,~ -Low                                      loop                        SR 3.3.2.2 SR 3.3.2.5
steam line F,G SR 3.3.2.1 SR 3.3.2.2 SR 3.3.2.5 0.( I (=.(
: e. High -High Steam Flow     1,2,3             2   per           F,G       SR 3.3.2.1       < 3.7E6        s 3.6E6 steam                        SR 3.3.2.2      ibm/hr 9       ibm/hr a line                        SR  3.3.2.5      755 pslg       755 pslg Coincident with               Refer to Function     1 (Safety Injection) for all Safety Injection                  initiation functions       and requirements.
s~
ibm/hr 9 i%i-ps+
IOUS Pr s 0.4E6 ibm/hr oI
~vpsl g I OOS Coincident with Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
Coincident with T,~ -Low 122 3
2 per loop F,G SR 3.3.2.1 a 543 F
SR 3.3.2.2 SR 3.3.2.5 a 545 F
e.
High -High Steam Flow 1,2,3 2 per steam line F,G SR 3.3.2.1 SR 3.3.2.2 SR 3.3.2.5
< 3.7E6 s 3.6E6 ibm/hr 9 ibm/hr a 755 pslg 755 pslg Coincident with Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
(b)
Except when both MSIVs are closed and de-activated.
(continued)
(continued)
(b) Except    when both MSIVs are closed and de-activated.
R.E.
R.E. Ginna Nuclear Power Plant                             3.3-26                                   Amendment No. 61
Ginna Nuclear Power Plant 3.3-26 Amendment No.
61


It ESFAS   Instrumentation B 3.3.2 BASES APPLICABLE             c. Steam Line Isolation Containment SAFETY ANALYSES,           Pressure Hi h Hi h (continued)
It
LCO, and APPLICABILITY               Containment Pressure -High High must be OPERABLE in MODES I, 2, and 3, because there is sufficient energy in the primary and secondary side to pressurize the containment following a pipe break. This would cause a significant increase in the containment pressure, thus allowing detection  and closure of the  MSIVs. The steam line isolation Function must    be OPERABLE in MODES 2 and 3 unless both MSIVs are closed and de-activated. In MODES 4, 5, and 6 the steam line isolation Function is not required to be OPERABLE  because there is not enough energy in the primary and secondary sides to pressurize the containment to the Containment Pressure High High setpoint.
 
: d. Steam Line   Isolation Hi h Steam Flow Coincident With Safet In 'ection and Coincident With T Low This Function provides closure of the MSIVs~w<'+'P an SLB or inadvertent openjyg of@g4G              'uring atmospheric relief or safety valv8to maintain at least one unfaulted SG as a heat sink for the reactor, and to limit the mass and energy release to containment.
ESFAS Instrumentation B 3.3.2 BASES APPLICABLE SAFETY ANALYSES,
: LCO, and APPLICABILITY c.
Steam Line Isolation Containment Pressure Hi h Hi h
(continued)
(continued)
R.E. Ginna Nuclear Power Plant     B 3.3-82                             Revision   6
Containment Pressure -High High must be OPERABLE in MODES I, 2, and 3, because there is sufficient energy in the primary and secondary side to pressurize the containment following a pipe break.
This would cause a significant increase in the containment
: pressure, thus allowing detection and closure of the MSIVs.
The steam line isolation Function must be OPERABLE in MODES 2 and 3 unless both MSIVs are closed and de-activated.
In MODES 4, 5, and 6 the steam line isolation Function is not required to be OPERABLE because there is not enough energy in the primary and secondary sides to pressurize the containment to the Containment Pressure High High setpoint.
d.
Steam Line Isolation Hi h Steam Flow Coincident With Safet In 'ection and Coincident With T Low This Function provides closure of the MSIVs~w<'+'P
'uring an SLB or inadvertent openjyg of@g4G atmospheric relief or safety valv8to maintain at least one unfaulted SG as a heat sink for the
: reactor, and to limit the mass and energy release to containment.
(continued)
R.E.
Ginna Nuclear Power Plant B 3.3-82 Revision 6


ESFAS Instrumentation B 3.3.2 BASES APPLICABLE                     d. Steam Line       Isolation Hi h Steam Flow Coincident SAFETY ANALYSES,                      With Safet In 'ection and Coincident With LCO, and                              T Low         (continued)
ESFAS Instrumentation B 3.3.2 BASES APPLICABLE SAFETY ANALYSES,
APPLICABILITY This Function must         be OPERABLE in HODES I, 2, and 3 when a     secondary side break or stuck open valve could result in rapid depressurization of the steam lines. The Steam Line Isolation Function is required to be OPERABLE in HODES 2 and 3 unless both HSIVs are closed and de-activated.
: LCO, and APPLICABILITY d.
This Function is not required to be OPERABLE in HODES 4, 5, and 6 because there is insufficient energy in the secondary side of the plant to have an   accident.
Steam Line Isolation Hi h Steam Flow Coincident With Safet In 'ection and Coincident With T Low (continued)
: e. Steam Line       Isolation Hi h Hi h Steam Flow Coincident With Safet         In 'ection tion provides closure of the HSI dur~in     a   team line brea (or dna         ent openin
This Function must be OPERABLE in HODES I, 2, and 3 when a secondary side break or stuck open valve could result in rapid depressurization of the steam lines.
                                    +of an     SG~ae&#xc3;p er>c re i               s     valve to ann a       east one unfaulted SG as a eat sink for the reactor, and to limit the mass and energy Value-          release to containment.
The Steam Line Isolation Function is required to be OPERABLE in HODES 2 and 3
    ~~ " c+po~ tin~~
unless both HSIVs are closed and de-activated.
FlOOWnlaid te  <-'
This Function is not required to be OPERABLE in HODES 4, 5, and 6 because there is insufficient energy in the secondary side of the plant to have an accident.
ba+5 po~   i tnv44 Two steam required to line flow   channels per steam be OPERABLE line for this Function.
e.
are These (oQQ    c                    are combined in a one-out-of-two logic t,o qp  ~or                        indicate high high steam flow in one steam line.
Steam Line Isolation Hi h Hi h Steam Flow Coincident With Safet In 'ection tion provides closure of the HSI dur~in a
FT-464 and FT-465 are the two channels required for steam line A. FT-474 and FT-475 are the two channels required for steam line B. Each steam line is considered a separate function for the purpose of this LCO. The steam flow transmitters provide control inputs, but the control function cannot initiate events that the Function acts to mitigate. Therefore, additional channels are not required to address control protection interaction issues.
team line brea (or dna ent openin
+of an SG~ae&#xc3;p er>c re i s
valve to ann a
east one unfaulted SG as a
eat sink for the reactor, and to limit the mass and energy release to containment.
FlOOWnlaid Value-
~~ " c+p te tin <-'
ba+5 o~ ~~
po~
i tnv44 (oQQ c
qp ~or Two steam line flow channels per steam line are required to be OPERABLE for this Function.
These are combined in a one-out-of-two logic t,o indicate high high steam flow in one steam line.
FT-464 and FT-465 are the two channels required for steam line A.
FT-474 and FT-475 are the two channels required for steam line B.
Each steam line is considered a separate function for the purpose of this LCO.
The steam flow transmitters provide control inputs, but the control function cannot initiate events that the Function acts to mitigate.
Therefore, additional channels are not required to address control protection interaction issues.
S+ta~
S+ta~
o~ ~o Alai +lAL a        ~~
o~
o ~OdlJ) A co~i iooapQ, ~~4~w, ~g c, HAII Q'ieo~ ~'ELJ clod~og
a ~o ~~ co~i iooapQ, ~~4~w, ~g Alai
                                      'L gi a ~+ io~eo           ~ cw~~~h         wi (continued)
+lAL o ~OdlJ) A
R.E. Ginna Nuclear Power Plant                 B   3.3-84                               Revision   6
'L gi wi c, HAIIQ'ieo~ ~'ELJ clod~og a ~+ io~eo ~ cw~~~h (continued)
R.E.
Ginna Nuclear Power Plant B 3.3-84 Revision 6


Attachment III Proposed Technical Specifications Included Pages:
Attachment III Proposed Technical Specifications Included Pages:
3.3-26
3.3-26


e     ESFAS   Instrumentation 3.3.2 Table 3.3.2-1 (page 2 of 3)
e ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 2 of 3)
Engineered Safety Feature Actuation System             Instrwentation APPLICABLE MODES OR OTHER SPECIFIED       REQUIRED                     'URVEILLANCE     ALLOHABLE       TRIP FUNCTION              COHDIT IOHS      CHANNELS         CONDITIONS     REQUIREMENTS       VALUE     SETPOINT
Engineered Safety Feature Actuation System Instrwentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED COHDITIOHS REQUIRED
: 4. Steam Line Isolation
'URVEILLANCE ALLOHABLE CHANNELS CONDITIONS REQUIREMENTS VALUE TRIP SETPOINT
: a. Manual   Initiation       1 2(b) 3(b)       1   per           D,G       SR 3.3.2.4         HA           HA loop
: 4. Steam Line Isolation a.
: b. Automatic Actuation       1,2( ) 3( )       2 trains           E,G       SR 3.3.2.7         HA           HA Logic and Actuation Relays
Manual Initiation 1 2(b) 3(b) 1 per loop D,G SR 3.3.2.4 HA HA
: c. Containment Pressure -High High           2(b) 3(b)                           F,G       SR 3.3.2.1     s 20 psig    s 18 psig 1
: b. Automatic Actuation Logic and Actuation Relays 1,2(
SR 3.3.2.2 SR 3.3.2.5
) 3( )
: d. High Steam Flow                2(b) ~ 3(b)      2 p  r            F,G        SR 3.3.2.1     s 0.66E6    s 0.4E6 1 ~                  steam                        "SR 3.3.2.2     ibm/hr g    ibm/hr g line                        SR 3.3.2.5     1005 psi   1005 psig Coincident with               Refer to Function       1 (Safety Injection) for   all Safety Injection                    initiation functions       and requirements.
2 trains E,G SR 3.3.2.7 HA HA
Coincident with           12         3         2   per           F,G       SR 3.3.2.1       a 543  F    a 545  F T~ -Low                                        loop                        SR 3.3.2.2 SR 3.3.2.5
: c. Containment Pressure -High High
: e. High -High Steam Flow     1,2( ),3( )         2   per           F,G       SR 3.3.2.1       s 3.7E6    s 3.6E6 steam                         SR 3.3.2.2     ibm/hr g    Ibm/hr g line                         SR 3.3.2.5     755 psig     755 psig Coincident with               Refer to Function       1 (Safety Injection) for   all Safety Injection                    initiation functions       and requirements.
: d. High Steam Flow 1 2(b) 3(b) 1 2(b) 3(b) 2 p r
(cont>nu )
~
(b) Except   when both MSIVs are closed and de-activated.
~
R.E. Ginna Nuclear Power Plant                               3.3-26                                   Amendment No. 61
steam line F,G F,G SR 3.3.2.1 SR 3.3.2.2 SR 3.3.2.5 SR 3.3.2.1 "SR 3.3.2.2 SR 3.3.2.5 s 20 psig s 0.66E6 ibm/hr g 1005 psi s
18 psig s 0.4E6 ibm/hr g 1005 psig Coincident with Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
Coincident with T~ -Low 12 3
2 per loop F,G SR 3.3.2.1 SR 3.3.2.2 SR 3.3.2.5 a 543 F
a 545 F
e.
High -High Steam Flow 1,2( ),3( )
2 per F,G SR 3.3.2.1 steam SR 3.3.2.2 line SR 3.3.2.5 s 3.7E6 ibm/hr g 755 psig s 3.6E6 Ibm/hr g 755 psig Coincident with Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
(b)
Except when both MSIVs are closed and de-activated.
(cont>nu
)
R.E.
Ginna Nuclear Power Plant 3.3-26 Amendment No.
61


I~
I~
0               4 P
0 P
                    ~
4 ~
        'A, Q) 1 4
4
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Latest revision as of 09:43, 8 January 2025

Proposed Tech Specs Revising Allowable Value & Trip Setpoint for High Steam Flow Input Into LCO Table 3.3.2-1,Function 4d (Main Steam Isolation) to Address Issues Identified in Rev Revised Setpoint Analysis Study
ML17264B039
Person / Time
Site: Ginna Constellation icon.png
Issue date: 09/29/1997
From:
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17264B034 List:
References
NUDOCS 9710020027
Download: ML17264B039 (8)


Text

Attachment II Marked Up Copy ofR.E. Ginna Nuclear Power Plant Technical Specifications Included Pages:

3.3-26 B 3.3-82*

, B 3.3-84" These bases pages are being provided for information only to show the changes RG8cE intends to make followingNRC approval ofthe I.AR. The bases are under RGB control for all changes in accordance with Specification 5.5.13.

9710020027 970929 PDR ADQCK 05000244 P

PDR

ESFAS Instrumentation 3.3.2 Table 3.3 '-1 (page 2 of 3)

Engineered safety Feature Actuation system Instrwlentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED SURVEILLANCE CHANNELS CONDITIONS REQUIREMENTS ALLOMABLE VALUE TRIP SETPOINT

4. Steam Line Isolation
a. Manual Initiation
b. Automatic Actuation Logic and Actuation Relays
c. Contaiment Pressure -High High (b) 3(b) 1 2(b) 3(b) 1 2(b) 3(b) 1 per loop 2 trains D,G E,G

-F,G SR 3.3.2.4 SR 3.3.2 '

SR 3.3.2.1 s 20 psig RR 3.3.2.2 SR 3.3.2.5 NA NA (C.RR-I

d. High Steam Flow 1 2(b) 3(b) 2 per

~

~

steam line F,G SR 3.3.2.1 SR 3.3.2.2 SR 3.3.2.5 0.( I (=.(

s~

ibm/hr 9 i%i-ps+

IOUS Pr s 0.4E6 ibm/hr oI

~vpsl g I OOS Coincident with Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

Coincident with T,~ -Low 122 3

2 per loop F,G SR 3.3.2.1 a 543 F

SR 3.3.2.2 SR 3.3.2.5 a 545 F

e.

High -High Steam Flow 1,2,3 2 per steam line F,G SR 3.3.2.1 SR 3.3.2.2 SR 3.3.2.5

< 3.7E6 s 3.6E6 ibm/hr 9 ibm/hr a 755 pslg 755 pslg Coincident with Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

(b)

Except when both MSIVs are closed and de-activated.

(continued)

R.E.

Ginna Nuclear Power Plant 3.3-26 Amendment No.

61

It

ESFAS Instrumentation B 3.3.2 BASES APPLICABLE SAFETY ANALYSES,

LCO, and APPLICABILITY c.

Steam Line Isolation Containment Pressure Hi h Hi h

(continued)

Containment Pressure -High High must be OPERABLE in MODES I, 2, and 3, because there is sufficient energy in the primary and secondary side to pressurize the containment following a pipe break.

This would cause a significant increase in the containment

pressure, thus allowing detection and closure of the MSIVs.

The steam line isolation Function must be OPERABLE in MODES 2 and 3 unless both MSIVs are closed and de-activated.

In MODES 4, 5, and 6 the steam line isolation Function is not required to be OPERABLE because there is not enough energy in the primary and secondary sides to pressurize the containment to the Containment Pressure High High setpoint.

d.

Steam Line Isolation Hi h Steam Flow Coincident With Safet In 'ection and Coincident With T Low This Function provides closure of the MSIVs~w<'+'P

'uring an SLB or inadvertent openjyg of@g4G atmospheric relief or safety valv8to maintain at least one unfaulted SG as a heat sink for the

reactor, and to limit the mass and energy release to containment.

(continued)

R.E.

Ginna Nuclear Power Plant B 3.3-82 Revision 6

ESFAS Instrumentation B 3.3.2 BASES APPLICABLE SAFETY ANALYSES,

LCO, and APPLICABILITY d.

Steam Line Isolation Hi h Steam Flow Coincident With Safet In 'ection and Coincident With T Low (continued)

This Function must be OPERABLE in HODES I, 2, and 3 when a secondary side break or stuck open valve could result in rapid depressurization of the steam lines.

The Steam Line Isolation Function is required to be OPERABLE in HODES 2 and 3

unless both HSIVs are closed and de-activated.

This Function is not required to be OPERABLE in HODES 4, 5, and 6 because there is insufficient energy in the secondary side of the plant to have an accident.

e.

Steam Line Isolation Hi h Hi h Steam Flow Coincident With Safet In 'ection tion provides closure of the HSI dur~in a

team line brea (or dna ent openin

+of an SG~aeÃp er>c re i s

valve to ann a

east one unfaulted SG as a

eat sink for the reactor, and to limit the mass and energy release to containment.

FlOOWnlaid Value-

~~ " c+p te tin <-'

ba+5 o~ ~~

po~

i tnv44 (oQQ c

qp ~or Two steam line flow channels per steam line are required to be OPERABLE for this Function.

These are combined in a one-out-of-two logic t,o indicate high high steam flow in one steam line.

FT-464 and FT-465 are the two channels required for steam line A.

FT-474 and FT-475 are the two channels required for steam line B.

Each steam line is considered a separate function for the purpose of this LCO.

The steam flow transmitters provide control inputs, but the control function cannot initiate events that the Function acts to mitigate.

Therefore, additional channels are not required to address control protection interaction issues.

S+ta~

o~

a ~o ~~ co~i iooapQ, ~~4~w, ~g Alai

+lAL o ~OdlJ) A

'L gi wi c, HAIIQ'ieo~ ~'ELJ clod~og a ~+ io~eo ~ cw~~~h (continued)

R.E.

Ginna Nuclear Power Plant B 3.3-84 Revision 6

Attachment III Proposed Technical Specifications Included Pages:

3.3-26

e ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 2 of 3)

Engineered Safety Feature Actuation System Instrwentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED COHDITIOHS REQUIRED

'URVEILLANCE ALLOHABLE CHANNELS CONDITIONS REQUIREMENTS VALUE TRIP SETPOINT

4. Steam Line Isolation a.

Manual Initiation 1 2(b) 3(b) 1 per loop D,G SR 3.3.2.4 HA HA

b. Automatic Actuation Logic and Actuation Relays 1,2(

) 3( )

2 trains E,G SR 3.3.2.7 HA HA

c. Containment Pressure -High High
d. High Steam Flow 1 2(b) 3(b) 1 2(b) 3(b) 2 p r

~

~

steam line F,G F,G SR 3.3.2.1 SR 3.3.2.2 SR 3.3.2.5 SR 3.3.2.1 "SR 3.3.2.2 SR 3.3.2.5 s 20 psig s 0.66E6 ibm/hr g 1005 psi s

18 psig s 0.4E6 ibm/hr g 1005 psig Coincident with Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

Coincident with T~ -Low 12 3

2 per loop F,G SR 3.3.2.1 SR 3.3.2.2 SR 3.3.2.5 a 543 F

a 545 F

e.

High -High Steam Flow 1,2( ),3( )

2 per F,G SR 3.3.2.1 steam SR 3.3.2.2 line SR 3.3.2.5 s 3.7E6 ibm/hr g 755 psig s 3.6E6 Ibm/hr g 755 psig Coincident with Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

(b)

Except when both MSIVs are closed and de-activated.

(cont>nu

)

R.E.

Ginna Nuclear Power Plant 3.3-26 Amendment No.

61

I~

0 P

4 ~

4

'A, Q) 1 U