ML19206A608

Certifies Tech Specs Change Request 7 to App a of Ol,Filed W/Nrc & Served on Chief Executives of Londonderry Township, Dauphin County,Pa by Us Mail

ML19206A608
Person / Time
Site:	Crane
Issue date:	05/10/1978
From:	Herbein J Metropolitan Edison Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML19206A607	List: ML19206A603 ML19206A608
References
NUDOCS 7904200244
Download: ML19206A608 (10)

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S' t I

TABLE 3.3-5 ENGINEERED S AFETi FEATURES RESPC!SE TIMES INITI ATING SIGNAL AND FUNCTION RESPONSE TI?1E IN SECONDS 1.

Manual a.

Safety Injection Not Applicable b.

Acactor Building Cooling Not Applicable c.

Reactor Stilding Isolation Not Applicable d.

Reactor Building Spray Not Applicable e.

Reacter Suildirg Sump Suction Not Applicable f.

Feedwater Latching Not Applicable 2.

Reactor Buildino Pressure Nich a.

High Pressure Inject"cn 1 25*/25**

b.

Low Pressure Injectian

< 25*/25**

c.

Reactor Building Conling

< 125 */125 **

d.

Reactor Building Isolation (1) Reactor Buil'ing Pt,rge Isolatica (2)

Reacter Bui" ding

-< 5*/5**

Isolation

< 60*/60**

(3) MU-V25 5 75*/75**

~~

e.

Control Building Emergency Ventilation (1)

Control Rcom Isolation

< 6*/5+*

(2)

Control Building HVAC 1 9C0*/900*

f.

Component Cooling Water Systems (1)

Decay Heat Closed Cooling

-< 3C0*/300"*

(2)

Nuclear Services Closed Cooling 1 95*/NA**

g.

Service Water System Nuclear Services River Water 1 g5*/95**

h.

Reactor Building Spray Valves 1 23*/23++

(1)

SS-V1A/3

~< 23 +/23 **

(2)

DH-VSA/3 1 3 5"/ 2 0*;' b)

{

TABLE 3.3-5 (continuedi ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSi~ TIPE IN SECCNDS 3.

Reactor Building Pressure--Hign-High a.

Reactor Building Spray Pumps 1 31 */31

• 4.

Reactor Coolant Pressure-Lcw a.

High Pressure Injection 1 25*/25**

b.

Low Pressure Injection

< 25*/25**

c.

Component Coolant Water System (1)

Decav Heat Closed Coolinc

< 300*/300**

(2)

Nuclear Services Closed Cooling i95*/NA**

~

d.

Service Water Systen (Nuclear Services River Water) 1 95*/95**

5.

Feedwcter Latching a.

Main Steam Isolation

< NA */124. 6 *

• b.

Feedwater Isolation (1)

FW-V30A/B

< NA*/9.2**

(2)

FW-Vl'iA/B 7 NA*/32.6**

(3)

FW-V?5A/B 7 NA*/14.6**

(4)

FW-Vi9A/3 iNA*/32.6**

6.

Emergency Feedwater Pump Actuation a.

Turbine Driven Pump

< NA*/29" b.

Motor Driven Pumps 5 29*/12**

TABLE NOTATION

• Diesel generator starting and sequence loading delays included.

Response time limit includes acvement of valves and attainment cf pump or blower discharge pressure.

• • Diesel generator starting and sequence loading delays no.: included.

Offsite pcwer available.

Response time limit includes movement cf valves and attainment of pump or bicwer discharge pressure.

(*)Respcnse ti e ap;'ien' ole for Reacter Eu:.iding ccoling and isolaticn onl--

t bb'AAQ su i

TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURE ACTUATICfl SYSTEMS INSTRUMENTATION S!!RVEILLANCE REQUIREMENTS a

i CilANNEL MODES IN Wi!ICil E

CilANNEL CllANNEL FUNCTIONAL SURVEILLAtlEE FUNCTIONAL UNIT CilECK CALIBRATION TEST REQUIRED 7

'j 7.

LOSS OF POWER g

a.

4.16 kv Emergency Cus Undervoltage (Loss of (Voltage i

1.

Emergency Bus

1. 2-lE and 2-2E S

R M

1,2,3 2.

Emergency Bus il2-3E and 2-4E S

R R

1,2,3 i

b.

4.16 kv Emergency Bus o

h tindervoltage (Degraded Vol tage) 1.

rmergency Bus g

ll2-lE and 2-2E S

R H

1,2,3 C"

2.

Emergency Bus o

1. 2-2E and 2-4E S

R R

1,2,3 O

(/1 8.

-CHFMICAL ADDITION SIGilAL IMactor 15u lding Cooling i

n.

and Isolution Ir Mintion

(

came as 2.n/b/c

)

b.

Sara'v Injection and

(

crune nu

1. n/b/c/d/o

)

IT avel Initint, ion N/A R

N/A 1, 2, 3, 14

.