ML20098A472

From kanterella
Jump to navigation Jump to search
Proposed Tech Specs,Relocating Functional Unit 6.b, FW Isolation-Low RCS Tavg Coincident W/Rt from TS Requirements Manual Licensee Controlled Document
ML20098A472
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 09/20/1995
From:
NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
To:
Shared Package
ML20098A467 List:
References
NUDOCS 9509260061
Download: ML20098A472 (12)
v • d • e


Text

_

1 l

"@j .c-gy"S TABLE 3.3-3 (Continued)

E C ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION k xh MINIMUM l

, oe TOTAL NO. CHANNELS CHANNELS APPLICABLE g 88FUNCTIONALUNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION l pog eao

4. Steam Line Isolation (continued)

~ "$ b. Automatic Actuation 2 1 2 1,2,3 -

20 Logic and Actuation Relays

c. Containment Pressure-- 3 2 2 1, 2, 3 ~ 18* l Hi-2
d. Steam Line 3/ steam line 2/ steam line 2/ steam line 1, 2, 3# 18* l

. Pressure-Low any steam line

e. Steam Generator

$ Pressure - Negative 3/ steam line 2/ steam line 2/ steam line 3** 18* l

= Rate-High any steam '

line

5. Turbine Trip
a. Automatic Actuation 2 1 2 1, 2 22 Logic and Actuation Relays
b. Steam Generator 4/stm. gen. 2/stm. gen. 3/stm. gen. 1, 2 18 Water Level--

k High-High (P-14)

E ~

5 6. Feedwater Isolation a

z a. Steam Generator Water 4/stm. gen. 2/stm. gen. 3/stm. gen. 1, 2 18

? L_evel--High-High (P-14) -

  • Coin ident
b. Low RCS T 1, 2 l with Reac r Tr

/ A +

y,

. ?*

TABLE 3.3-3 (Continued) .

8 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION MINIMUM

$' TOTAL NO. CHANNELS CHANNELS APPLICABLE c: FUNCTIONAL UNIT OF CHANNELS z TO TRIP OPERABLE MODES ACTION El b.*,e: Safety Injection '

o' See Item 1. above for all Safety Injection initiating functions and requirements.

. 7. Emergency Feedwater

a. Manual Initiation (1) Motor driven pump 1 1 1 (2) Turbine driven pump 2 1,2,3 21 1 2 1,2,3 21
b. Automatic Actuation Logic 2 1 2 1,2,3 R,a and Actuation Relays 20 g> c. Stm. Gen. Water Level--

g; Low-Low Start Motor-Driven Pump 4/stm. gen. 2/stm. gen. 3/stm. gen.

and Start Turbine - 1,2,3 18 Driven Pump

d. Safety Injection Start Motor-Driven Pump and Turbine-Driven Pump See Item 1. above for all Safety Injection initiating functions and requirements.

k/I e. Loss-of-Offsite Power N

Start Motor-Driven '

T Pump and Turbine- '

sj s Driven Pump See Item 9 for loss of-Offsite Power initiating functions and requirements.

8. Automatic Switchover to Containment Sump .

bh

_ a. Automatic Actuation 2 1 2 1,2,3,4 Logic and Actuation 13 '

Relays ,

22 d .

_ _ _ _--_-_-._--_ _- _ _ _ _ _ _ e ~e- -_ -  %, _ _- .___m-__ -- ____--

l l

w TA8LE 3.3-4 (Continued) '

8o ENGINEERED SAFETY FEATURES ACTUATION SYSTEN INSTRUNENTATION TRIP SETPOINTS .

3

  • SENSOR TOTAL g FUNCTIONAL UNIT ALLOWANCE (TA) Z ERROR ll M (S) TRIP SETPOINT ALLOWA8LE VALUE i, g 4. Steam Line Isolation

' a. Manual Initiation (System) N.A. N.A. N.A. N.A. N.A.

b. Automatic Actuation Logic N.A. N.A. N.A. N.A. N.A.

i and Actuation Relays

c. Containment Pressure--Hi-2 5.2 0.71 1.67 <4.3 psig 15.3 psig m d. Steam Line Pressure--Low 13.1 10.71 1.63 >585 psig >568 psig*

A _

w e. Steam Generator Pressure - 3.0 0.5 0 <100 psi <123 psi **

4 m

Negative Rate--High _

5. Turbine Trip
a. Automatic Actuation Logic N.A. N.A. N.A. N.A. N.A.

, Actuation Relays

b. Steam Generator Water 4.0 2.24 0.55 <86.0% of <87.7% of narrow Level--High-High (P-14)

- narrow range range instrument instrument span.

span.

O 6.

Feedwater Is'o lation -

a. Steam Generator Water 4.0 2.24 0.55 <86.0% of Level--Hi-Hi-(P-14) <87.7% of narrow narrow range range instrument

' instrument span.

h V V s an.

b. L w RCS T Co ncident El 4 1 2 1. 8 >5 4*F >5 . 2*l-ith React r Tr~p h  % Safety Injec ion N.A.

A N.A. N.A.

A N.A. N.A.

(m)I

l ,..

l 9

TABLE 4.3-2 (Continued) '

ENGINEERED SAFETY F EATDIES ACTATION SYS"EN INSTRLMENTATION SJ (VE; _ANC E LEQUI l:EMENS

~

i TRIP ANALOG ACTUATING MODES

.g t

CHANNEL DEVICE MASTER SLAVE FOR WHICH

  • CHANNEL CHANNEL CHANNEL l

OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE i

FUNCTIONA. UNI' CHECK CALIBRATION TEST TEST LOGIC TEST IflI IESI IS REOUIRED l 4. Steam .ine . solation

a. Manual Initiation N.A. N.A. N.A. R N.A. N.A. N.A. 1, 2, 3
b. b'S:rstem?

u;omatuc Actuation M.A. N.A. N.A. N.A. M(1) M(1) Q 1, 2, 3 s

, Logic and Actuation l Relays

c. Containment Pressure- S R Q N.A. N.A. N.A. N.A. 1, 2, 3 Hi-2 l ,
d. Steam Line S R Q N.A. N.A. N.A. N.A. 1, 2, 3 l i s" Pressure-Low '
e. Steam Line Pressure- S R Q N.A. M.A. R.A. N.A. 3 l
  • p Negative Rate-High w

" i

5. Turbine Trip '
a. Automatic Actuation N.A. N.A. N.A. N.A. M(1) M(1) Q 1, 2

, Logic and Actuation l Relays  :'

b. Steam Generator Water S R Q N.A. N.A. N.A. N.A. 1, 2 l Level-High-High (P-14)  !
6. Feedwater Isolation
a. Steam Generator Water S R Q N.A. N.A. N.A. N.A. 1, 2 l

, k b Q N.A. 1, 2 l E with Re r Tr - ^ -

g safety In ec on See Item 1. above for all Safpty injection Surveillance Requirements.

[

o

7. Emergency Feedwater Qcg

{ a. Manual Initiation 1 Motor-driven pump N.A. N.A. N.A. R N.A. N.A. N.A. 1, 2, 3 2)jTurbine-drivenpump N.A. N.A. N.A. R N.A. N.A. N.A. 1, 2, 3 i

1  :

. i

  • r.  !

i . i 4  :

i III. 'Retvec of Proposed Chamees l 1 Attached is a retype of the affected Technical Specification pages to include the proposed changes, i The retype reflects the currently issued version of the Technical Specifications. Pending Technical ,

i Specification changes or Technical Specification changes issued subsequent to this submittal are

. not reflected in the enclosed retype. The enclosed retype should be checked for continuity with ,

j the Technical Specifications prior to issuance.

l

{ Revision bars are provided in the right hand margin to designate a change in the text.

J t -

! l i

) I i

I i

1 I

i I

3

? i i .

I, h

l 4 f i .

i

. e 1 I I

4 d

i r

i 4 .

4

- -v -

- -, -,v ,- --, , _ ~ , ,,-.--. - - . ,

.. . . . . .- . . - . . . - . . . - - - - . . . . . . . . - . . - . . - . . . . . . . . . - . . - . . - . . ~ . . . _ - ~ . .. . . . .

~

co TABLE 3.3-3 (Continued) .

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL ~NO. CHANNELS CHANNELS APPLICABLE E FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION q i

- 4. Steam Line Isolation (continued)

b. Automatic Actuation 2 1 2 1, 2. 3 20 Logic and Actuation

! Relays i

c. Containment Pressure-- 3 2 2 1. 2. 3 18*

Hi-2

d. Steam Line 3/ steam line 2/ steam line 2/ steam line li 2. 3# 18*

, 5:3 Pressure-Low any steam A line .

.Y e. Steam Generator  !

g Pressure - Negative 3/ steam line 2/ steam line 2/ steam line 3** 18*

Rate-High any steam i line I

5. Turbine Trio i
a. Automatic Actuation 2 1 2 1. 2 22 Logic and Actuation Relays ,

2,. b. Steam Generator 4/stm. gen. 2/stm. gen. 3/stm. gen. 1. 2 18 5 Water Level--

a High-High (P-14) 8 a 6. Feedwater Isolation k a. Steam Generator Water 4/stm. gen. 2/stm. gen. 3/stm. gen. 1. 2 18 i

Level--High-High (P-14)  !

l

b. Safety Injection See Item 1. above for all Safety Injection initiating functions- r and requirements. j i

[

g TABLE 3.3-3 (Continued 1 -

b ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION l

8

^

MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE E FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION m i

- 7. Emergency Feedwater

a. Manual Initiation (1) Motor driven pump 1 1 1 1.2.3 21 '

(2) Turbine driven pump 2 1 2 1. 2. 3 21

b. Automatic Actuation Logic 2 1 2 1. 2. 3 20 and Actuation Relays
c. Stm. Gen. Water Level--

R a

Low-Low Y Start Motor-Driven Pump 4/stm. gen. 2/stm. gen. 3/stm. gen. 1. 2. 3 18 y and Start Turbine -

Driven Pump

d. Safety Injection Start Motor-Driven Pump See Item 1. above for all Safety Injection initiating functions and and Turbine-Driven Pump requirements.
e. Loss-of-Offsite Power Start Motor-Driven See Item 9 for Loss-of-Offsite Power initiating functions and Pump and Turbine- requirements.

Driven Pump R 8. Automatic Switchover to Containment Sump

[

a

a. Automatic Actuation 2 1 2 1.2.3.4 13 Logic and Actuation

& Relays

.,~..

i

l. @_ TABLE 3.3-4 (Continued) i

~

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS c SENSOR z TOTAL ERROR

-4 FUNCTIONAL UNIT (S)

ALLOWANCE (TA) Z TRIP SETPOINT ALLOWABLE VALUE

4. Steam Line Isolation
a. Manual Initiation (System) N.A. N.A. N.A. N.A. N.A.
b. Automatic Actuation Logic N.A. N.A. N.A. N.A. N . A .-

and Actuation Relays

c. Containment Pressure--Hi-2 5.2 0.71 1.67 s4.3 psig s5.3 psig y d. Steam Line Pressure--Low 13.1 10.71 1.63 2585 psig 2568 psig*

Y e. Steam Generator Pressure - 3.0 0.5 0 s100 psi 5123 psi **

ER Negative Rate--High

5. Turbine Trip
a. Automatic Actuation Logic N.A. N.A. N.A. N.A. N.A.

Actuation Relays

b. Steam Generator Water 4.0 2.24 0.55 586.0% of s87.7% of narrow Level--High-High (P-14) narrow range range instrument instrument span.

span.

{ 6. Feedwater Isolation -

g

a. Steam Generator Water 4.0 2.24 0.55 586.0% of s87.7% of narrow Level--Hi-Hi-(P-14) narrow range range instrument z instrument span.

o span.

b. Safety Injection N.A. N.A. N.A. N.A. N.A.

_ .~; -

t TABLE 4.3-2 (Continued) ,

h ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION g SURVEILLANCE REOUIREMENTS .

7 TRIP c ANALOG ACTUATING MODES -

z CHANNEL DEVICE MASTER SLAVE FOR WHICH U CHANNEL CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE

- FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEST T_E_SI IS REQUIRED ,

4. Steam Line Isolation
a. Manual Initiation N.A. N.A. N.A. R N.A. N.A. N.A. 1. 2. 3 (System)
b. Automatic Actuation N.A. N.A. N.A. N.A. M(1) M(1) Q 1,2,3 Logic and Actuation Relays
c. Containment Pressure- S R Q N.A. N.A. N.A. N.A. 1, 2. 3 Hi-2 ,

a d. Steam Line S R Q N.A. N.A. N.A. N.A. 1. 2. 3  :

2 Pressure-Low a e. Steam Line Pressure- S R Q N.A. N.A. N.A. N.A. 3 4, Negative Rate-High

" i

5. Turbine Trip
a. Automatic Actuation N.A. N.A. N.A. N.A. M(1) M(1) Q 1. 2 Logic and Actuation Relays
b. Steam Generator Water S R Q N.A. N.A. N.A. N.A. 1, 2 Level-High-High (P-14) l ,
6. Feedwater Isolation k a. Steam Generator Water S R Q N.A. N.A. N.A. N.A. 1. 2  ;

a Level--High-High (P-14) g b. Safety Injection See Item 1. above for all Safety Injection Surveillance Requirements.

3

[ 7. Emergency Feedwater O

a. Manual Initiation

~M

1) Motor-driven pump N.A. N.A. N.A. R N.A. N.A. N.A. 1. 2. 3
2) Turbine-driven pump N.A. N.A. N.A. R N.A. N.A. N.A. 1. 2. 3 i

s b_, - , _ _ , _ _. , . . . . - ~ . . _ . - - - . - - , . _ , . , ,m-. m.-__ , . , - . ..--.r- , . - . . - ,-. __.___-____________.m.-._..____._.._.m.-__-

_ _ __ .- _ _ . _ _ ____ __ _- ._ _ __. .~ .__

s.

e ' .

i 1

IV. - ' Determination of Sinnificant Hazanis for Proposed Channes

1. The proposed changes do not involve a significant increase in the probability or consequences of l
, an accident previously evaluated.

The change considered for the relocation of the feedwater isolation setpoint from the Technical

Specifications does not impose any new performance requirements on any system or component which could subsequently cause associated design criteria to be exceeded. The structural and  ;

j functional integrity of the plant's structures, systems and components is maintained. This change 1 does not affect the initiators of any transients evaluated in the Updated Final Safety Analysis .

{

Report (UFSAR).

i j- The sequence of obtaining feedwater isolation on low T., coincident with reactor trip is not

] credited in any of the LOCA and non-LOCA accidents evaluated in the UFSAR. Feedwater 1

isolation is initiated for other reasons such as a Safety injection (SI) actuation. This change is ,

administrative in nature, in that it relocates the function from the Technical Specifications to the j Seabrook Station Technical Requirements Manual and there are no changes to the plant's 1 structures, systems and components.

i Since, for the reasons given above, the results of the UFSAR analyses are not affected by the j implementation of the change, there is, therefore, no adverse impact on the radiological ,

! consequences of accidents reported in the UFSAR. Furthermore, this change'does not degrade fission product barriers assumed in the dose consequence analysis such as the fuel cladding, the 4 reactor pressure vessel, and containment. The performance and integrity of accident mitigating

! structures, systems and components such as the Emergency Feedwater and Safety injection systems, are not affected by the change. Consequently, the ability of these systems to limit i radiological consequences as described in the UFSAR is not adversely affected. Based on the l' l above, the proposed changes do not involve a significant increase in the probability or 4

consequences of an accident previously evaluated.

2. The proposed changes do not create the possibility of a new or different kind ofaccidentfrom any accident previously evaluated.

l The proposed change does not create any new failure modes for any structure, system or

component. All design and performance criteria will continue to be met and no new single failure scenario is created that is not bounded by the accidents described in the UFSAR. The proposed I change to the Technical Specifications does not introduce any new challenges to structures, l systems and components that could introduce a new type of accident. Therefore the proposed l changes do not create the possibility of a new or different kind of accident from any accident I previously evaluated.
3. The proposed changes do not result in a sigmficant reduction in the margin of safety.

4 The accidents analyzed in the UFSAR have been reviewed relative to the feedwater isolation on low RCS T,y coincident with reactor trip. The applicable design criteria and the pertinent licensing basis acceptance criteria continue to be met. The margin of safety as defined in the Bases to the Technical Specifications is not reduced and the design and safety analysis limits remain applicable.

4 5

1 i i

~

s.

Y. Proposed Schedule for License Amendment Issuance and Effectiveness North Atlantic requests NRC review of License Amendment Request 95-08 and issuance of a license amendment having immediate effectiveness by December 1,1995.

6

i.

1

)

VI. ' Environmental Impact Assessment North Atlantic has reviewed the proposed license amendment against the criteria of 10CFR51.22 for environmental considerations. The proposed changes do not involve a significant hazards consideration, nor increase the types and amounts of effluent that may be released offsite, nor significantly increase individual or cumulative occupational radiation exposures. Based on the foregoing, North Atlantic concludes that the proposed change meets the criteria delineated in 10CFR51.22(c)(9) for a categorical exclusion from the requirements for an Environmental Impact Statement.

7

Retrieved from "https://kanterella.com/w/index.php?title=ML20098A472&oldid=2799853"