ML17059B287
| ML17059B287 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 09/17/1996 |
| From: | Dromerick A NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17059B288 | List: |
| References | |
| NUDOCS 9609200321 | |
| Download: ML17059B287 (18) | |
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t UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205554001 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-41'0 NINE MILE POINT NUCLEA STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
77 License No.
NPF-69 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated May 15,
- 1996, 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 1'.
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 assur ance (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 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 Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating -License No. NPF-69 is hereby amended to read as follows:
9e092003ax 9e09<7 PDR ADOCK 050004l0 P
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(2)
Tec i al S ecifications and nvironmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached
- hereto, as revised through Amendment No.
77 are hereby incorporated into this license.
Niagara Mohawk Power Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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 Alexan er W. Dromerick, Acting Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Date of Issuance:
september 17, 1996
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 77 TO FACILITY OPERATING LICENS NO.
NPF-69 DOCKET NO. 50-410 Revise Appendix A as follows:
Remove Pa es v
3/4 3-17 3/4 3-19A 3/4 3-25 3/4 3-28 t
P v
3/4 3-17 3/4 3-19A 3/4 3-19B*
3/4 3-25 3/4 3-28 ew page
LI I
P RATI REA TIVTY NTR Y TE (Continued) 3/4.1.5 STANDBY LIQUID CONTROL SYSTEM...................
3/41-19 Figure 3.1.5-1 Sodium Pentaborate Tank Volume vs. Concentration Requirements...........,.........................
3/4 1-22 4
E Dl TRIB I
LIMIT 3/4.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE 3/42-1 3/4.2.2 AVERAGE POWER RANGE MONITOR SETPOINTS........... ~.....
3/4 2-2 3/4.2.3 MINIMUMCRITICAL POWER RATIO (ODYN OPTION B).......,.....
3/4 2-3 3/4.2.4 LINEAR HEAT GENERATION RATE........ ~...................
3/4 2-5 4.
IN TR MENT Tl N
3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION.............
3/4 3-'I Table 3.3.1-1 Reactor Protection System Instrumentation...............
~. 3/4 3-2 Table 3.3.1-'2 Reactor Protection System Response Times................
3/4 3-6 Table 4.3.1.1-1 Reactor Protection System Instrumentation Surveillance equirements...,,........,...........,....,.......,...
~.....
3/4 3 7 R
3/4.3.2 ISOLATIONACTUATIONINSTRUMENTATION....................
3/4 3-10 Table 3.3.2-1 Isolation Actuation Instrumentation..........................
3/4 3-12 Table 3.3.2-2 Isolation Actuation Instrumentation Setpoints..................
3/4 3-17 Figure 3.3.2-1 Allowable and Trip Setpoint Values for the Main Steam Line Tunnel Lead Enclosure..................................
3/4 3-198 Table 3.3.2-3 Isolation System Instrumentation Response Time..........
~ ~....
3/4 3-20 Table 3.3.2-4 Valve Groups and Associated Isolation Signals..................
3/4 3-22 Table 4.3.2.1-1 Isolation Actuation Instrumentation Surveillance Requirements....
3/4 3-25 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATIONINSTRUMENTATION 3/4 3-29 Table 3.3.3-1 Emergency Core Cooling System Actuation Instrumentation........
3/4 3-30 Table 3.3.3-2 Emergency Core Cooling System Actuation Instrumentation Setpolflts o
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3/4 3-35 Table 3.3.3-3 Emergency Core Cooling System Response Times...............
3/4 3-39 NINE MILE POINT - UNIT 2 v
Amendment No. 6 7/
TABLE..2-2 IS LATI N A T ATI N IN TR MENTATI N ETP IN t
TRIPF N
I N
Primr n
in n
I lain in l (Continued) a.
Reactor Vessel Water Level*
- 1) Low, Low, Low, Level 1
- 2) Low, Low, Level 2
- 3) Low, Level 3 b.
Drywall Pressure - High c.
- 1) Radiation - High**
- 2) Pressure
- Low
- 3) Flow - High d.
Main Steam Line Tunnel
- 1) Temperature - High
- 2) hTemperature - High
e.
Condenser Vacuum Low f.
RHR Equipment Area Temperature
- High (HXs/AS.B Pump Rooms) 9.
Reactor Vessel Pressure - High (RHR Cut-in Permissive) h.
SGTS Exhaust - High Radiation
~17.8 in.,
+108.8 in.
>159.3 in.
s1.68 psig s3x Full Power Background z766 psig s121.5 psid s 167.2'F s70.0 F
s148.2~F a8.5 in Hg vacuum s 135'F s128 psig s 5.7x10 pCi/cc LL WABLEVAL a10.8 in.
. a101.8
<n.
a 157.8 in.
s1.88 psig s3.6x Full Power Backgrourid
.a746 psig s122.8 psid i'
170.6'F s71.7'F,.
151.60F a7..6 in. Hg vacuum
-. s144.5OF:
s148 psig s1.0x10 pCi/cc
zzm K
m 0Oz I
Cz ISOLATIONACTUATIONIN TRUMENTATIONSETP IN 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 and 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 /> after completion of the hydrogen injection test. At reactor power levels below 20% rated power hydrogen injection shall be terminated. and control rod withdrawal is prohibited until the Main Steam Line Radiation Monitor trip setpoint is restored to its pre-test value.
The trip setpoint and allowable value for a channel may be established based on Figure 3.3.2-1, if:
a.
the actual ambient temperature reading for all operable channels in the Lead Enclosure area are equal to or greater than the ambient temperature used as the basis for the setpoint, and M
CO b.
C.
the absence of steam leaks in the Main Steam Line Tunnel Lead Enclosure area is verified by visual inspection prior to increasing a channel setpoiht, and a surveillance is implemented in accordance with Note "d" of Table 4.3.2.1-1.
CL z0 Ob
0,
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180 170 C.'
CL
~ (o 160
~m E)
I-Xl 150 Albwable Value Trip Setpoint 80 90
>>0 120 1.30 140 Lead Enclosure Ambient Temperature
('F)
Used as Basis for Setpoint FIGURE 3.3.2-1 Allowable and Trip Setpoint Values for the Main Steam Line Tunnel Lead Enclosure NINE MILE POINT - UNIT 2 3/4 3-19B Amendment No.
77
A
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TRIP F 1.
Primr n
in n
I I in inl CHANNEL CHANNEL FUNCTION CHANNEL
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OPERATION CONDITIONS FOR WHICH SURVEILLANCEIS RE RED a.
Reactor Vessel Water Level IS LATI N A T ATI N IN TRUMENTATI N RVEILLAN E RE IRENlE 60 CB b.
C.
d.
1)
Low, Low, Low, Level 1
2)
Low, Low, Level 2 3)
Low, Level 3 Drywell Pressure - High Main Steam Line 1)
Radiation - High 2)
Pressure
- Low 3)
Flow - High Main Steam Line Tunnel S
S S
S S
S S
0 00 0
0 00 R(a)
R(a)
R(a)
R(a)
R R(a)
R(a) 1,2,3 1,2;3and*
1,2,3 1,2,3 1,2,3 1
- 1. 2. 3 1)
Temperature - High S
2) hTemperature - High S
3)
Temperature - High MSL Lead S(d)
Enclosure 00 0
R(b)
R(b)
R(b) 1,2,3 1, 2.3
- 1. 2. 3 zO z
zO e.
Condenser Vacuum - Low RHR Equipment Area Temperature-High (HXs/A58 Pump Rooms)
Reactor Vessel Pressure High (RHR Cut-in Permissive)
S S
S-0 0
0 R(a)
R(b)
R(a) 2** 3**
1,2. 3
- 1. 2.3
I
ELN E
I E
BLE During CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
This only applies to secondary containment isolation and automatic start of SGTS.
1 When any turbine stop valve is greater than 90% open and/or when the key-locked condenser low vacuum bypass switch is open (in Normal position).
t When handling irradiated fuel in the reactor building and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel; (a)
Perform the calibration procedure for the trip unit setpoint at least once per 92 days.
(b)
Calibration excludes sensors; sensor response and comparison shall be done in lieu of.
(c)
Manual isolation pushbuttons are tested at least once per operating cycle during shutdown.
All other circuitry associated with manual isolation shall receive a CHANNEL FUNCTIONALTEST at least once per 92 days as part of the circuitry required to be tested for the automatic system isolation.
(d)
In addition to the normal shift channel check, if a channel setpoint has been established using Figure 3.3.2-1, then once per shift the actual ambient temperature reading for all.
operable channels in the Lead Enclosure area shall be verified to be equal to or greater than
. the ambient temperature used as the basis for the setpoint.
NINE MILE POINT - UNIT 2 3/4 3-28 AMENDMENTNO. ki(, 6 77
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