ML17056B178
| ML17056B178 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 12/07/1990 |
| From: | Greenman E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17056B179 | List: |
| References | |
| NUDOCS 9012140119 | |
| Download: ML17056B178 (52) | |
Text
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION.UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
1i9 License No.
DPR-63 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated November 28, 1990, as supplemented on December 4, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 Comnission; C.
There is reasonable assurance (i) 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 conducted in compliance with the Comssion'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 ComIission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.
DPR-63 is hereby amended to read as follows:
90 1 21 +01
+0002+0 19 901207 pDR PQOCK p
p
f C
I
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 119, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Edward G.
- Greenman, Acting Assistant Director for Region I Reactors Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Date of Issuance:
December 7,
1990
I I
ATTACHMENT TO LICENSE AMENDMENT
'MENDMENT NO.
119 =TO FACILITY OPERATING LICENSE NO.
DPR<<63 DOCKET NO. 50-220 Revise Appendix A as follows:
Remove Pa es 191 192 193 196a 197 198 199 200 204 205 207 208 210 211 212a 213 215 224 225a 226 227 231 232a Insert Pa es 191 192 193 196a 197 198 199 200 204 205 207 208 210 211 212a 213 215 224 225a 226 227 231 232a
I C
l
Table 3.6.2a Niniaua No.
of Tripped or Operable Niniaua No. of Operable Instrument Channels per Operable Reactor Node Switc Position in Which~
Function Nust Be OD D
C/l CL S-IO l/l (1)
Nanual Scram (2)
High Reactor Pressure (3)
High Drywell Pressure (4)
Low Reactor Water Level 2
< 1080 psig
< 3.5 psig
> 53 inches (Indicator Scale) x x
x x
x x
)
x (a)
(a>
I x
x x
(5)
High Water Level Scram Discharge Volume
< 45 gal.
(b) x x
Amendment No. Pf, 7P
))9 191
J I
Table 3.6.2a (cont'd)
INSTRUMENTATION THAT INITIATES S RAM Limitin Condition for 0 era ion P rameter Minimum No.
of Tripped or Operable Tri S stems Minimum No. of Operable Instrument Channels per Operable Tri S stem o
Set Point Reactor Mode Switch Position in Which Function Must Be 0 erable (6)
Main-Steam-Line Isolation Valve Position (7)
High Radiation Main-Steam-Line (8)
Shutdown Position of Reactor Mode Switch 4(h)
< 10 percent valve closure from full open 5 times normal background at rated power'"'c)
(c) x x
x x
(k) x x
(9)
Neutron Flux (a)
IRM (i) 3(d)
< 96 percent of full scale (g)
(g)
(g)
Amendment No. p1, 57.
192
I
Table 3.6.2a (cont'd)
INSTRUMENTATION THAT INITIATES SCRAM Limiting Condition for Operation Parameter Minimum No.
of Tripped or Operable Minimum No. of Operable Instrument Channels per Operable Tri S stem o
Set Point Reactor Mode Switch Position in Which Function Must Be.
0 er ble Oa Vl Q.
ap 4
4 dJ OC C/l (ii) Inoperative 2
3(d)
(b)
APRM (i)
Upscale 2
3(e)
Figure 2.1.1 X
X X
(ii) Inoperative 2
3(e)
X X
(iii) Downscale 2
3(e) 5 percent of full scale (g)
(g) (g)
(10)
Turbine Stop Valve Closure
< 10t valve closure (ll)
Generator Load Rejection Amendment No.
pp
] ] 9 193
NOTES FOR TABLES 3.6.2a and 4.6.2a cont (n)
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of the hydrogen injection test with the reactor power at greater than 20% rated power, the normal full-power radiation background level and associated trip and alarm setpoints may be changed based on a calculated value of the radiation level expected during the test.
The background radiation level and associated trip and alarm setpoints may be adjusted during the test program based on either calculations or measurements of actual radiation levels resulting from hydrogen injection.
The background radiation level shall be determined and associated trip and alarm setpoints shall be reset within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re-establishing normal radiation levels.
after completion of the hydrogen injection or within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of establishing reactor power levels below 20% rated power, while these functions are required to be operable.
At reactor power levels below 20% rated
- power, hydrogen injection shall be terminated and the injection system secured.
(o)
A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillances without placing the Trip System in the tripped condition provided at least one operable channel in the same trip system is monitoring that parameter.
This time interval is extended up to 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> for the High Radiation Main-Steam Line Instrument Channel Calibration surveillance.
Amendment No.
g7 119 196a
I
Table 3.6.2b INSTRUMENTATION THAT INITIATES PRIMARY COOLANT SYSTEM OR CONTAINMENT ISOLATION Limitin Condition for 0 eration Parameter Minimum No.
of Tripped or Operable Tri S stems Minimum No. of Operable Instrument Channels per Operable Tri S stem f
Set Point Reactor Mode Switch Position in Which Function Must Be 0 erable I
O 1D PRIMARY COOLANT ISOLATION (Main Steam,
- Cleanup, and Shutdown)
(1) Low-Low Reactor Water Level 5 inches (Indicator Scale)
X X
(2)
Manual MAIN-STEAM-LINE ISOLATION X
X X
X (3)
High Steam Flow Main-Steam Line 105 psid X
X Amendment No. p', g, gg ]19 1.97
l
Table 3.6.2b (cont'd)
I STRUMENTATION THAT INITIATES PRIMARY CO LANT SYSTEM OR CONTAINMENT ISOLATION Limitin Condition for 0 eration P r meter Minimum No.
of Tripped or Operable Tri S
tems Minimum No. of Operable Instrument Channels per Operable Tri S
s em f
Set Point Reactor Mode Switch Position in Which Function Must Be 0 erable I
CL O
Ql 5-ca C) u)
n v)
(4)
High Radiation Main Steam Line (5)
Low Reactor Pressure 5 times normal background at rated power 850 psig x
x (6)
Low-Low-Low Condenser Vacuum 7 in. mercury vacuum (a) x (7)
High Temperature Main Steam Line Tunnel
< 200F x
x Amendment No. p$,
5T 119 198
Table 3.6.2b (cont'd)
INSTRUMENTATION THAT INITIATES PRIMARY OOLANT SYSTEM OR CONTAINMENT ISOLATION Limitin ondition for eration P rameter Minimum No.
of Tripped or Operable Tri S
em Minimum No. of Operable Instrument Channels per Operable Tri S stem f
Set Point Reactor Mode Switch Position in Which Function Must Be 0 erable I
O Ctl CL e
c CY LE UP SYSTEM I
LATION (8)
High Area Temperature H TD WN OOLING YSTEM ISOLATIO 190 X
X X
X (9)
High Area Temperature TAI MENT I OLATI N 170 X
X X
X (10)
Low-Low Reactor Water Amendment No. p', pf, 37 119 5 inches (Indicator Scale)
(c)
X X
199
Table 3.6.2b (cont'd)
INSTRUMENTATION THAT INITIATES PRIMARY CO LANT SYSTEM OR CONTAINMENT ISOLATION Limi in Condition for 0 eration P rameter Minimum No.
of Tripped or Operable Tri S
em Minimum No. of Operable Instrument Channels per Operable Tri S stem f
Set Point Reactor Mode Switch Position in Which Function Must Be 0 erable O
CA (11)
High Drywell Pressure (12)
Manual
< 3.5 psig (c)
(b)
(b)
X X
X X
Amendment No.
200
TES F
R TABLES 3
.2b and 4
6 2b (a)
May be'ypassed in the refuel and startup positions of the reactor mode switch when reactor pressure is less than 600 psi.
(b)
May be bypassed when necessary for containment inerting.
(c)
May be bypassed in the shutdown mode whenever the reactor coolant system temperature is less t than 215'F.
(d)
Only the trip circuit will be calibrated and tested at the frequencies specified in Table 4.6.2b, the primary sensor will be calibrated and tested once per operating cycle.
(e)
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of the hydrogen injection test with the reactor power at greater than 20% rated power, the normal full-power radiation background level and associated trip and alarm setpoints may be changed based on a calculated value of the radiation level expected during the test.
The background radiation level and associated trip and alarm setpoints may be adjusted during the test program based on either calculations or measurements of actual radiation levels resulting from hydrogen injection.
The background radiation level shall be determined and associated trip and alarm setpoints-shall be reset within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re-establishing normal radiation levels after completion of the hydrogen injection or within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of establishing reactor power levels below 20% rated power, while these functions are required to be operable.
At reactor power levels below 20t rated power hydrogen injection shall be terminated and the injection system secured.
(f)
A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillances without placing the Trip System in the tripped condition provided at least one operable channel in the same Trip system is monitoring that parameter.
This time interval is extended up to 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> for the High Radiation Main-Steam Line Instrument Channel Calibration Surveillance.
Amendment Nn. pf, Pf, ding 119 204
I
Table 3.6.2c E TATI THAT INITIATE R ISOLATES EMERGENCY COOLING Limi in ondition for er tion P rm er Minimum No.
of Tripped or Operable Tri Minimum No. of Operable Instrument Channels per Operable em d
S t-Point Reactor Mode Switch Position in Which Function Must Be 0 erable I
Oo
+J Vl QJ Cl tV EMER E
Y OOLING (1)
High-Reactor Pressure
< 1080 psig (b)
X X
(2)
Low-Low Reactor Water Level 5 inches (b)
(Indicator Scale)
X X
E ER E
Y OLI (for each of two systems)
(3)
High Steam Flow Emergency Cooling System 2 (a) 19 psid X
X Amendment Po.
65 119 205
OTES FOR TABLES 3.6.2c AND 4.6.2c (a)
Each of two differential pressure switches provide inputs to one instrument channel in each trip system.
(b)
May be bypassed in the cold shutdown condition.
(c)
Only the trip circuit will be calibrated and tested at the frequencies specified in ~
Table 4.6.2c, the primary sensor will be calibrated and tested once per operating cycle.
(d)
A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillances without placing the Trip System in the tripped condition provided at least one operable channel in the same Trip system is monitoring that parameter.
Amendment Nc.
3A, jg 1]9 May 2 1980 207
Table 3.6.2d I
TR NE TATI THA I p
l ~ )
L mi in ndi i f r n
Pra r
Ninilua No.
of Tripped or Operable Tri 0
Niniaua No. of Operable Instrument Channels Per Operable ri m
~Set i'eactor Node Switch Position in Which Function Nust Be r
1 Oi Cl Ol CX CL 5
IO Vl TART RE PRAY P
NPS (1)
High Drywell Pressure
< 3.5 psig (d) x (a)
(a)
(2)
Low-Low Reactor Water Level
)
5 inches (b) x x
x (Indicator Scale)
Reactor Pressure and either (1) or (2) above.
365 psig x
x x
x Amendment No. Pf, g, 7P 119 208
TABLE 2D42d (a)
May be bypassed when necessary for containment inerting.
(b)
May be bypassed when necessary for performing major maintenance as specified in Specification 2.1.1.e.
(c)
Only the trip circuit will be calibrated and tested at the frequencies specified in Table 4.6.2d, the primary sensor will be calibrated and tested once per operating cycle.
(d)
May be bypassed when necessary for integrated leak rate testing.
(e)
The instrumentation that initiates the Core Spray System is not required to be operable, if there is no fuel in the reactor vessel.
(f)
One instrument channel in each trip system may be bypassed in the cold shutdown and refuel conditions during the Spring 1986 refueling outage to perform the emergency condenser piping replacement.
(g)
A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillances without placing the Trip System in the tripped condition provided at least one operable channel in the same Trip system is monitoring that parameter.
anendment No.
)A, p1, 7p 119 210
r
Table 3.6.2e I STRUMENTATION THAT INITIATES CONTAINMENT SPRAY Limitin Condition for 0 eration P r meter Minimum No.
of Tripped or Operable Tri S
m Minimum No. of Operable Instrument Channels per Operable Tri S stem c
Set Point Reactor Mode Switch Position in Which Function Must Be 0 erable Oo C/0 (1)a.
High Drywell Pressure 3.5 psig (a)
X X
and b.
Low-Low Reactor Water Level 5 inches (a)
(Indicator Scale)
X X
Amendment No.
211
(s
TE FOR TABLES 2e AND 4 2e (a)
May be bypassed in the shutdown mode whenever the reactor coolant temperature is less than 215oF.
(b)
Only the trip circuit will be calibrated and tested at the frequencies specified in Table 4.6.2e, the primary sensor will be calibrated and tested once per operating cycle.
(c)
A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillances without placing the Trip System in the tripped condition provided at least one operable channel in the same Trip system is monitoring that parameter.
Amendment No.
g7 119 Nay 2 1980 212a
tr
Table 3.6.2f INSTRUMENTATION THAT INITIATES AUTO DEPRESSURIZATION Limitin Condition for 0 eration Parameter Minimum No.
of Tripped or Operable Tri S stems Minimum No. of Operable Instrument Channels Per Operable Tri S stem d
Set Point Reactor Mode Switch Position in Which Function Must Be 0 erable INITIATION (1)a.
Low-Low-Low Reactor Water Level 2 (a) 2 (a)
> -10 inches (Indicator Scale)
(b)
(b) x and b.
High Drywell Pressure 2 (a) 2 (a)
< 3.5 psig (b)
(b) x
- greater than
(>) means less negative Amendment No. A 119 213
~
V
BLE 2f (a) ~h instrument channels in ~~ trip system are required to be energized to initiate auto depressurization.
One trip system is povered from power board 102 and the other trip system from pover. board 103.
-(b)
Nay be bypassed when the reactor pressure is less than 110 psig and the reactor coolant temperature is less than the corresponding saturation temperature.
(c)
Only the trip circuit will be calibrated and tested at the frequencies specified in Table 4.6.2f, the primary sensor vill be calibrated and tested once per operating cycle.
(d)
A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillances vithout placing the Trip System in the tripped condition provided at least one operable channel in the same Trip system is monitoring that parameter.
Amendment No.
g7 119 215
V
Table 3.6.2h VA UM P MP I LATIO Limi in Condi i n for ra ion r
m r
Minimum No.
of Tripped or Operable Tri Minimum No. of Operable Instrument Channels Per Operable Tri em b
Set Point Reactor Mode Switch Position in Which Function Must Be 0 er ble I AL A UUM PUMP High Radiation Main Steam Line 5 times normal"'ackground X
X X
Amendment No.:54/
119 224
I I
NOTES FOR TABLES 3.6.2h and 4.6.2h (a)
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the planned start of the hydrogen injection test with the reactor power at greater than 20% rated power, the normal full-power radiation background level and associated trip and alarm setpoints may be changed based on a calculated value of the radiation level expected during the test.
The background radiation level and associated trip and alarm setpoints may be adjusted during the test program based on either calculations or measurements of actual radiation levels resulting from hydrogen injection.
The background radiation level shall be determined and associated trip and alarm setpoints shall be reset within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of re-establishing normal radiation levels after completion of the hydrogen injection or within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of establishing reactor power levels below 20% rated power, while these functions are required to be operable.
At reactor power levels below 20% rated power hydrogen injection shall be terminated and the injection system secured.
(b)
A channel may be placed in an operable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillances without placing the Trip System in the tripped condition provided at least one operable channel in the same Trip System is monitoring that parameter.
This time interval is extended up to 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> for the High Radiation Main-Steam Line Instrument Channel Calibration surveillance.
Amendment No.
225a
Table 3.6.2i DIE EL GENERATOR INITIATION Limi in Condition for 0 er tion Reactor Hode Svitch Position in Vhich Function Hust be 0 erable ZiKMRX<<
Loss of Pover Total No.
of h nn l Channels to Tri Hinimum Channels 0
rable c
CL Q
r QJ S
ns 4J CA OC l/l
- a. 4.16kV PB 102/103 Emergency Bus Undervoltage (Loss of Voltage) 3 per Bus 2 per Bus 2 per Bus X
X X
X
- b. 4.16kV PB 102/103 Emergency Bus Undervoltage (Degraded Voltage) 3 per Bus 2 per Bus 2 per Bus X
X X
X (1) If one out of three channels becomes inoperable, the inoperable channel vill be placed in the trip condition.
Amendment No.
4N 226
L,~
Table 4.6.2i DIE EL ENERATOR INITIATION rv ill nc Re uir m n PiKRa~r Sensor Instrument" n 1 T t
Instrument~
Channel Calibration Loss of Power a.
4.16kV PB 102/103 Emergency Bus Undervoltage (Loss of Voltage)
NA Once per month Once per refueling cycle b.
4.16kV PB 102/103 Emergency Bus Undervoltage (Degraded Voltage)
Once per month Once per refueling cycle (a)
The instrument channel test demonstrate the operability of the instrument channel by simulating.an undervoltage condition to verify that the tripping logic functions properly.
(b)
The instrument channel calibration will demonstrate the operability of the instrument channel by simulating an undervoltage condition to verify that the tripping logic functions properly. In addition, a sensor calibration will be performed to verify the set points listed in Table 3.6.2.i.
(c)
A channel
<<ay be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillances without placing the Trip System in the tripped condition provided at least one operable channel in the same Trip System is monitoring that parameter.
Amendment No.
@/ 119 227
)
Table 3.6.2k HIGH PRESSURE COOLANT INJECTION Limitin Condition for 0 eration Parameter Minimum No.
of Tripped or Operable Tri S stems Minimum No. of Operable Instrument Channels Per Operable Tri S stem c
Set-Point Reactor Mode Svitch Position in Qhich Function Must Be 0 erable (1) Lov Reactor Vater Level
> 53 inches (Indicator Scale)
CL O
r QJ S
4 e
c
~
0 l/)
CL tl) t5 (a)
(a) x (2) Automatic Turbine Trip (a)
(a) x Amendment No. g', Q, gT 119May 2 1980
-231
~
4 4
NOTES FOR TABLES 3.6.2k AND 4.6.2k (a)
Hay be bypassed vhen the reactor pressure is less than 110 psig and the reactor coolant temperature is less than the corresponding saturation temperature.
(b)
Only the trip circuit will be calibrated and tested at the frequencies specified in Table 4.6.2k, the primary sensor vill be calibrated and tested once per operating cycle.
(c)
A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillances vithout placing the Trip System in the tripped condition provided at least one operable channel in the same Trip system is monitoring that parameter.
Amendment No. /, g/ 119 May 2 1980 232a
k I