Text

Corrected Safety Evaluation Supporting Amend 67 to License NPF-58
	ML20080F707
Person / Time
Site:	Perry
Issue date:	11/22/1994
From:	; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20080F709	List: ML20080F707; ML20080F857;
References
	NUDOCS 9501300178
	Download: ML20080F707 (23)
	v • d • e

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ATTACHMENT TO CORRECTION LETTER FOR AMENDMENT NO. 67 i

FACILITY OPERATING LICENSE NO. NPF-58 i

DOCKET NO. 50-440 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages, j

i Remove Insert 3/4 3-26 3/4 3-26 3/4 3-39 3/4 3-39 3/4 3-100 3/4 3-100 3/4 3-102 3/4 3-102 t

t t

f C

l 9501300178 950124 i

PDR ADOCK 05000440 P

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y TABLE 4.3.2.1-1 (Continted) m 7

ISOLATION ACTUATION INSTRUNENTATION SURVEILLANCE REQUIREMENTS E

CHANNEL OPERATIONAL Z

CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE.REOUIRED 6.

RHR SYSTEM IS0tATION a.

RHR Equipment Area Ambient Temperature - High S

Q R

1, 2, 3 b.

RHR Equipment Area A Temperature - High S

Q R

1, 2, 3 c.

RHR/RCIC Steam Line Flow - High S

Q R(6) 1, 2, 3 d.

Reactor Vessel Water Level -

g Low, Level 3 ##

S Q

R

1, 2, 3 y

e.

Reactor Vessel (RHR Cut-in g

Perwissive) Pressure - High S

Q R(6) 1, 2, 3 f.

Drywell Pressure - High ##

S Q

R(*)

1, 2, 3 g.

Manual Initiation NA R

NA 1, 2, 3

When nandling irradiated fuel in the primary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
When any turbine stop valve is greater than 90% open and/or the key locked bypass switch is k
in the normal position.
OPERATIONAL CONDITION 1 or 2 when the mechanical vacuum pump lines are not isolated.
2 f During CORE ALTERATION and operations with a potential for draining the reactor vessel.
5 (a) Each train or logic channel shall be tested at least every other 92 days.
(b) Calibrate trip unit setpoint at least once per 92 days.
.=
These Trip Functions (Ib, 3b, 6d, and 6f) utilize instruments which are common to RPS instrumentation.
.E
}
TABLE 4.3.3.1-1 (Continued)
o 7
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE RCOUIREMENTS E
CHANNEL OPERATIONAL Z
CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED C.
DIVISION 3 TRIP SYSTEM 1.
HPCS SYSTEM a.
Reactor Vessel Water Level -
Low, Level 2 5
Q R")
1, 2, 3, 4*, 5*
b.
Drywell Pressure-High #f S
Q R'
1, 2, 3 c.
Reactor Vessel Water Level -
High, Level 8 S
Q R(*)
1, 2, 3, 4*, 5*
d.
Condensate Storage Tank Level -
Low S
Q R(*)
1, 2, 3, 4*, 5*
e.
Suppression Pool Water wi Level - High S
Q R
1, 2, 3, 4*, 5*
.f.
HPCS Pump Discharge Pressure -
w J,
High S
Q R)
1, 2, 3, 4*, 5*
g.
HPCS System Flow Rate - Low S
Q R
1, 2, 3, 4*, 5*
h.
Manual Initiation ##
NA R
NA 1, 2, 3, 4*, 5*
D.
LOSS OF POWER 1.
4.16 kV Emergency Bus Under-NA NA R
1, 2, 3, 4**, 5**
voltage (Loss of Voltage) 2.
4.16 kv Emergency Bus Under-S M
R 1, 2, 3, 4**, 5**
voltage (Degraded Voltage)
Not required to be OPERABLE when reactor steam dome pressure is less than or equal to 100 psig.
g-
The injection function of Drywell Pressure - High and Manual Initiation are not required to be g
OPERABLE with indicated reactor vessel water level on the wide range instrument greater than the Level 8 setpoint coincident with reactor pressure less than 450 psig.
F
When the system is required to be OPERABLE per Specification 3.b.2 or 3.5.3.
Required when ESF equipment is required to be OPERABLE.
O (a) Calibrate trip unit setpoint at least once per 92 days.
l
TABLE 3.3.9-1
3g PLANT SYSTEMS ACTUATION INSTRUMENTATION MINIMUM APPLICABLE E
OPERABLE CHANNELS OPERAT!0NAL Z
TRIP FUNCTION PER TRIP SYSTEM ")
CONDITIONS ACTION 1.
CONTAINMENT SPRAY SYSTEM a.
Drywell Pressure - High 2
1, 2, 3 130 b.
Containment Pressure - High 2
1,2,3 131 c.
Reactor Vessel Water Level - Low, Level 1 2
1, 2, 3 130 d.
Timers (1) Subsystem A and B (2) Subsystem B (1.5 m(nute timer)10 minute timer) 1 1, 2, 3 131 a
1 1, 2, 3 131 g
e.
Manual Initiation 1
1, 2, 3 133 h
2.
FEEDWATER SYSTEM / MAIN TURBINE TRIP SYSTEM y
a.
Reactor Vessel Water Level - High, Level 8 3
1 132 3.
SUPPRESSION POOL MAKEUP SYSTEM a.
Drywell Pressure - High 2
1, 2, 3 130 b.
Reactor Vessel Water Level - Low, Level 1 2
1, 2, 3 130 c.
Suppression Pool Water Level - Low 2
1,2,3 131
[
d.
Suppression Pool Makeup Timer 1
1, 2, 3 131 e.
SPMU Manual Jr.ttiall6n 1
1, 2, 3 133 5
,E (a) When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated ACTIONS may be delayed as follows:
(a) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Trip Function 1.d.(2); and (b) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Trip Functions other than 1.d.(2) provided the associated Trip Function maintains u
Plant Systems actuation capability.
m.
2.=_
o TABLE 4.3.9.1-1 E
5!
PLANT SYSTEMS ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS c
CHANNEL OPERATIONAL 5
CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH
[ TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED 1.
CONTAINMENT SPRAY SYSTEM a.
Drywell Pressure - High S
Q R*
1, 2, 3 b.
Containment Pressure - High S
Q R*
1, 2, 3 c.
Reactor Vessel Water level -
Low, Level 1 S
Q R*
1, 2, 3 d.
Timers (1) Subsystem A and B NA Q
R 1, 2, 3 (2) Subsystem B NA Q
R 1, 2, 3 e.
Manual Initiation NA R
NA 1, 2, 3 2.
FEEDWATER SYSTEM / MAIN TURBINE TRIP SYSTEM
[
a.
Reactor Vessel Water Level - High, 2,
level 8 S
Q R*
1 l
3.
SUPPRESSION POOL MAKEUP SYSTEM a.
Drywell Pressure - High S
Q R*
1, 2, 3 b.
Reactor Vessel Water Level -
Low, level 1 S
Q R*
1, 2, 3 c.
Suppression Pool Water Level - Low S
Q R*
1, 2, 3 d.
Suppression Pool Makeup Timer NA Q
Q 1, 2, 3 e.
SPMU Manual Initiation NA R
NA 1, 2, 3 g
8 k
Calibrate trip unit setpoint at least once per 92 days.
l
.?
.

ML20080F707

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