ML20070N170
| ML20070N170 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 04/28/1994 |
| From: | Hopkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070N174 | List: |
| References | |
| NUDOCS 9405050196 | |
| Download: ML20070N170 (11) | |
Text
___
t t>R *EGU e
.71 ft UNITED STATES
}
[
iZ j
NUCLEAR REGULATORY COMMISSION f
. WASHINGTON, D.C. 20666-0001 f
THE CLEVELAND ELECTRIC ILLUMINATING COMPANY. ET AL.
'CKET N0. 50-440 PERRY NUCLEAR POWER PLANT. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 59 License No. NPF-58 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by The Cleveland Electric Illuminating Company, Centerior Service Company, Duquesne Light Company, Ohio Edison Company, Pennsylvania Power Company, and Toledo Edison Company (the licensees) dated January 19, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be ccnducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-58 is hereby -
amended to read as follows:
9405050196 940428 PDR ADOCK 05000440 P
______u
(2)
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 59 are hereby incorporated into this license.
The Cleveland Electric Illuminating Company shall operate the facility in accordance with the Technical Specifi-cations and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Jon B. Hopkins, Sr. Froject Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
April 28, 1994
ATTACHMENT TO LICENSE AMENDMENT NO. 59 FACILITY OPERATING LICENSE N0. NPF-58 l
l DOCKET N0. 50-440 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Overleaf pages are provided to maintain document completeness.
Remove Insert 3/4 3-13 3/4 3-13 3/4 3-19 3/4 3-19 3/4 3-22 3/4 3-22 3/4 3-25 3/4 3-25 1
I I
1 i
]
1 1
TABLE 3.3.2__1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION vE
- o MINIMUM APPLICABLE 7
TRIP FUNCTION OPERABLE CHANNELS OPERATIONAL E
PER TRIP SYSTEM (a)
CONDITION ACTION 5.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION RCIC Steam Line Flow - High a.
1 1, 2, 3 27 b.
RCIC Steam Supply Pressure -
Low 1
1, 2, 3 27 c.
RCIC Turbine Exhaust Diaphragm Pressure - High 2
1,2,3 27 d.
RCIC Equipment Room Ambient Temperature - High 1
1,2,3 27 w
e.
Deleted w
f.
Main Steam Line Tunnel h
Ambient Temperature - High 1
1, 2, 3 27 g.
Main Steam Line Tunnel A Temperature - High 1
1,2,3 27' h.
Main Steam Line Tunnel Temperature Timer 1
1,2,3 27 i.
RHR Equipment Room Ambient j
Temperature - High a.
1/ Area 1, 2, 3 27 2
j.
RHR Equipment Room A E
Temperature - High
=
1/ Area 1, 2, 3 27 i
P k.
RCIC Steam Line Flow High g
Timer 1
h 1, 2, 3 27 1.
Drywell Pressure - High 1
1,2,3 27 m.
Manual Initiation 1
1, 2, 3 26 1
e TABLE 3.3.2-2 (Continued)
_lSOLATION ACTUATION INSTRUMENTATION SETPOINTS m"
g IRIP FUNCTION TRIP SETPOINT ALLOWABLE 5.
VALUE E
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION RCIC Steam Line Flow - High a.
s 290" H O 2
s 298.5" H O b.
RCIC Steam Supply Pressure - Low 2
2 60 psig 2 55 psig RCIC Turbine Exhaust Diaphragm c.
Pressure - High s 10 psig s 20 psig d.
- RCIC Equipment Room Ambient
. Temperature - High 5 143.4*F s 145.9"F e.
Deleted w
f.
Main Steam Line Tunnel Ambient 2
Temperature - High
$ 154.4*F s 158.9'F g.
Main Steam Line Tunnel A Temperature - High s 103.6*F 5 107.4*F h.
Main Steam Line Tunnel Temperature Timer 5 29 minutes k
s 30 minutes i.
RHR Equipment Room Ambient
{
g Temperature - High a
s 157.4*F i
k J.
RHR Equipment Room s 159.9'F A Temperature - High 2
F 5 50.65*F s 52.4*F i
k.
RCIC Steam Flow High Timer E
3 secondss ts 13 seconds 1.
Drywell Pressure - High 3 secondss is 13 seconds a
5 1.68 psig m.
Manual Initiation
-5 1.88 psig i
O NA NA
\\
- - - - - - - - - - - - ~ -
TABLE 3.3.2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION _
A E
MINIMUM APPLICABLE 7
TRIP FUNCTION OPERABLE CHANNELS OPERATIONAL E
PER TRIP SYSTEM (al
_ CONDITION ACTION 5.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION RCIC Steam Line Flow - High a.
1 1, 2, 3 27 b.
RCIC Steam Supply Pressure -
LOW l
1, 2, 3 27 c.
RCIC Turbine Exhaust Diaphragm Pressure - High 2
1,2,3 27 d.
RCIC Equipment Room Ambient Temperature - High 1
1, 2, 3 27 w
e.
Deleted 1
w f.
Main Steam Line Tunnel h
Ambient Temperature - High 1
1,2,3 27 g.
Main Steam Line Tunnel A Temperature - High 1
1, 2, 3 27 h.
Main Steam Line Tunnel
^
Temperature Timer 1
1, 2, 3 27 i.
RHR Equipment Room Ambient j
Temperature - High o.
1/ Area 1, 2, 3 27 Po J.
RHR Equipment Room A A
Temperature - High
=
?
1/ Area 1, 2, 3 27 k.
RCIC Steam Line Flow High g
Timer 1
1, 2, 3 27 1.
Drywell Pressure - High 1
1, 2, 3 27 m.
Manual Initiation 1
1, 2, 3 26
.. -. - - - - - ~ ~ - -~ - " ' ' ^ ^ ' ' - ~ '
I
_ TABLE 3.3.2-1 (Continued)
E ISOLATION ACTUATION INSTRUMENTATION y
i x*
HINIMUM APPLICABLE
[
_ TRIP FUNCTION OPERABLE CHANNELS OPERATIONAL PER TRIP SYSTEM fa)
CONDITION ACTION
=Z 6.
RHR SYSTEM ISOLATION RHR Equipment Area Ambient a.
Temperature - High
-1/ Area 1, 2, 3 28 i
b.
RHR Equipment Area A Temperature - High 1/ Area 1, 2, 3 28 c.
RHR/RCIC Steam Line Flow - High 1
1, 2, 3 28 d.
Reactor Vessel Water w
Level - Low, Level 3 2
1,2,3 28 1
Reactor Vessel (RHR Cut-in w
e.
Permissive) Pressure -
High 2
1, 2, 3 28 f.
Drywell Pressure - High 2
1,2,3 28 g.
Manual Initiation 2
1, 2, 3 26 g.
.E i
4 I
_ TABLE 3.3.2-2 (Continued)
~
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS
,5
_ TRIP FUNCTION TRIP SETPOINT 5.
U E
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION Q
a.
RCIC Steam Line Flow - High s 290" H O
~
2 s 298.5" H O b.
RCIC Steam Supply Pressure - Low 2
1 60 psig 1 55 psig RCIC Turbine Exhaust Diaphragm c.
Pressure - High s 10 psig
^
s 20 psig d.
.RCIC Equipment Room Ambient
. Temperature - High 5 143.4*F s 145.9*F e.
Deleted w
f.
Main Steam Line Tunnel Ambient i
Temperature - High s 154.4*F s 158.9'F g.
Main Steam Line Tunnel e
A Temperature - High 5 103.6*F 5 107.4*F h.
Main Steam Line Tunnel Temperature Timer 5 29 minutes j
k i.'
RHR Equipment Room Ambient s 30 minutes a
Temperature - High 5 157.4*F 5 159.9*F g
J.
RHR Equipment Room l
A Temperature - High 2O s 50.65'F
(
k.
RCIC Steam Flow High 5 52.4*F Timer 3 secondss ts 13 seconds 3 secondss ts 13 seconds 1.
Drywel.' f :ssure - High s 1.68 psig m.
Manual ' itiation s 1.88 psig O
NA 1
NA A*
t
TABLE 3.3.2-2 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS m
E2 2
TRIP FUNCTION TRIP SETPOINT ALLOWABLE 6.
RHR SYSTEM ISOLATION
_ VALUE t
5
-d RHR Equipment Area Ambient a.
Temperature - High 5 157.4*F b.
s 159.9'F RHR Equipment Area A Temperature -
High s 50.65'F s 52.4*F RHR/RCIC Steam Line Flow - High c.
s 52.1" H O d.
2 Reactor Vessel Water Level - Low 5 55.6" H O 2
Level 3 2 177.7 inches
- Reactor Vessel (RHR Cut-in 2'177.1 inches e.
'{
Permissive) Pressure - High 5 135 psig f.
Drywell Pressure - High s 150 psig s 1.68 psig g.
Manual Initiation s 1.88 psig NA NA F
mg a
8 See Bases Figure B 3/4 3-1 c+
L (d
e
- - ~ - - - ' ^
TABLE 3.3.2-3 JSOLATION SYSTEM INSTRUMENTATION RE TRIP FUNCTION RESPONSE TIME (Secondsl#
l.
E.RIMARY CONTAINMENT ISOLATIO_N Reactor Vessel Wat a.
b.
Drywell Pressure er Level - Low, Level 2 NA
\\
High Containment and Dr NA c.
Radiation - High*,ywell Purge Exhaust Plenum l
d.
Reactor Vessel Water Level - Low, Level 1 s 10("
Manual Initiation e.
NA NA 2.
MAIN STEAM LINE ISOLATION Reactor Yessel Water Level - Low, Level I a.
b.
Main Steam Line Radiation - High s 1.0*/s 10'0" Main Steam Line Pressure - Low c.
NA d.
Main Steam Line Flow - High
< 1.0*/s 10(0" Condenser Vacuum - Low 2 0.S /s 10'0" e.
f.
Main Steam Line Tunnel Temperature - HighNA Main Steam Line Tunnel A Temperature - High g.
NA h.
Turbine Building Main Steam Line NA Temperature - High i.
Manual Initiation NA NA 3.
SECONDARY CONTAINMENT ISOLATION Reactor Vessel Wa a.
Drywell Pressure ter Level - Low, Level 2 b.
High NA c.
Manual Initiation NA NA
- 4. REACTOR WATER CLEANUP SYSTEM ISOLATION a.
A Flow - High b.
A Flow Timer NA Equipment Area Temperature - High c.
NA d.
Equipment Area A Temperature - Hi NA Reactor Vessel Water Level - Low,gh e.
NA f.
level 2 NA Main Steam Line Tunnel Ambient Temperature - High SLCS InitiationMain Steam Line Tunnel A Temperature - High g.
NA h.
NA i.
Manual Initiation NA NA PERRY - UNIT 1 3/4 3-21 Amendment NoS8
TABLE 3.3.2-3 (Continued)
_ ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION RESPONSE TIME (Seconds)#
5.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION RCIC Steam Line Flow - High a.
b.
RCIC Steam Supply Pressure - Low NA NA RCIC Turbine Exhaust Diaphragm Pressure - High c.
d.
NA RCIC Equipment Room Ambient Temperature - HighNA Deleted e.
f.
Main Steam Line Tunnel Ambient l
Temperature - High NA Main Steam Line Tunnel A Temperature - High g.
NA h.
Main Steam Line Tunnel Temperature Timer i.
-NA RHR Equipment Room Ambient Temperature - High NA j.
RHR Equipment Room A Temperature - High k.
NA RCIC Steam Line Flow High Timer 1.
Drywell Pressure - High NA m.
Manual Initiation NA NA 6.
RHR SYSTEM ISOLATION RHR Equipment Area Ambient Temperature - High a.
b.
NA RHR Equipment Area A Temperature - High NA RHR/RCIC Steam Line Flow - Hi c.
Reactor Vessel Water Level gh d.
NA Low, level 3 NA Reactor Vessel (RHR Cut-in Permissive) e.
Pressure - High f.
Drywell Pressure - High NA g.
Manual Initiation NA NA (a) diesel generator starting and sequence loading delays t
(b)
Radiation detectors are exempt from response time testing.
shall be measured from detector output or the input of the firstResponse time electronic component in the channel.
- Isolation system instrumentation response time for MSIVs only generator delays assumed.
No diesel Isolation system instrumentation response time for associated valves except MSIVs.
- Isolation sy:, tem instrumentation response time specified for the Trip Function actuating each containment isolation valve shall be added to the isolation time for each valve to obtain ISOLATION SYSTEM for each valve.
PERRY - UNIT I 3/4 3-22 Amendment No. A),59
TABLE 4.3.2.1-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REOUIREMENTS yg CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL
. CONDITIONS IN WHICH i
g TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED 5
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION RCIC Steam Line Flow - High S
M R'b' e
a.
5 b.
RCIC Steam Supply Pressure -
1, 2, 3 Low S
M R'b'
~
RCIC Turbine Exhaust Diaphragm 1, 2, 3 c.
Pressure - High S
M R'b' 1, 2, 3 d.
RCIC Equipment Room Ambient Temperature - High S
M R
e.
Deleted 1, 2, 3 f.
Main Steam Line Tunnel Ambient l
i Temperature - High S
M R
i g.
Main Steam Line Tunnel 1, 2, 3 4
A Temperature - High S
M R
h.
Main Steam Line' Tunnel 1, 2, 3 Temperature Timer NA M
R 1, 2, 3
~
R 1.
RHR Equipment Room Ambient
+
Temperature - High S
M R
1, 2, 3 y
j.
RHR Equipment Room A g
Temperature - High S
M R
k.
RCIC Steam Line Flow 1, 2, 3 i
High Timer NA M
R 1, 2, 3
'l.
Drywell Pressure - High S
M R(b) i m.
Manual Initiation NA R
NA 1, 2, 3 2, 3 P
am i
a tD 3
t E
i i
i
I
-u9 IABLE 4.3.2.1-1 (Continued)
ISOLA 110N ACTUAllON INSTRUMLNIATION SURVEIL CHANNEL.
1 RIP FUNCTION tilANNEL FUNCT10NAL CHANNEL OPERATIONAL e
i 5
6.
RHR SYSTEM ISOLATION J;llEQ_
TEST CONDITIONS IN WHICH d
CAllBRATION_
SURVElllANCE REQUIRED RHR Equipment Area Ambient a.
Temperature - High S
M R
b.
RHR Equipment Area 1, 2, 3 A iemperature - High S
M R
RHR/RCIC Steam Line 1, 2, 3 c.
Flow - High S
M R*'
d.
1, 2, 3 low, tevel 3 S
M R*'
Reactor Vessel (RHR Cut-in 1, 2, 3 e.
Permissive) Pressure - High S
M R*'
y f.
Drywell Pressure - High 1,.2, 3 S
M R *'
g.
Manual Initiation 1, 2, 3 NA R
NA 1
1, 2, 3
\\
=
When handling irradiated fuel in the primary containment a d d
- with a potential for draining the reactor vessel.
B When any turbine stop valve is greater than 90% open and/or the kuring COR n
normal position.
- During CORE ALTERATION ey locked bypass switch is in the (a) Each train or logic channel shall be tested at least everand operations with a potent u,
jb,) Calibrate trip unit setpoint at least once per 31 d y other 31 days.
OPERATIONAL CONDITION 1 or 2 when the mechanical vacuum pump li ays.
nes are not isolated.
1 I
l I
.