ML20011E261
| ML20011E261 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/02/1990 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Northeast Nuclear Energy Co (NNECO) |
| Shared Package | |
| ML20011E262 | List: |
| References | |
| NPF-49-A-045 NUDOCS 9002130018 | |
| Download: ML20011E261 (10) | |
Text
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'g UNITED STATES NUCLEAR REGULATORY COMMISSION n
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WASHINGTON, D. C. 20656 l
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S NORTHEAST NUCLEAR ENERGY COMPANY. ET AL.
DOCKET NO. 50-423 i
MILLSTONE NUCLEAR POWER STATION, UNIT N0. 3 i
AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 45 l
License No. NPF-49 1.
The Nuclear Regulatory Comission (the Commission) has found that:
The app (lications for amendment by Northeast Nuclear Energy Company, A.
et al. thelicensee)datedOctober17andOctober 19, 1989, comply 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
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provisions of the Act, and the rules and regulations of the Comission; C.
Thereisreasonableassurance(1)thattheactivitiesauthorizedby L
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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendirent is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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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-49 is hereby amended to read as follows:
(2) Technical Specifications l
l The Technical Specifications contained in Appendix A, as revised l
i through Amendment No. 45
, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. The licensee 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 of issuance.
FOR THE NUCLEAR REG ATORY COMMISSION I
t 1
oh T. Stolz, Directo Pro ect Directorate 1-
' ision of Reactor Projects - I/II Office of Nuclear Reactor Reguletion l
Attachment:
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Changes to the Technical Specifications Date of Issuance:
February 2, 1990 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 45 FACILTIY OPERATING LICENSE NO. NPF-49_
DOCKET NO. 50-423 Replace the following sages of the Appendix A Technical Specifications with the enclosed pages. Tia revised pages are identified by amendment nunter and contain vertical lines indicating the areas of change. The corresponding overleaf pages are provided to maintain document completeness.
Rymove Insert 3/4 3-1 3/4 3-1 3/4 3-16 3/4 3-16 3/4 3-39 3/4 3-39 3/4 3-40 3/4 3-40 3/4 3-41 3/4 3-41 w
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3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION i
3.3.1 As a minimum, the Reactor Trip System instrumentation channels
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and interlocks of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in Table 3.3-2.
APPLICABILITY: As shown in Table 3.31.
i ACTION:
As shown in Table 3.3 1.
SURVEILLANCE REOUIREMFNTS 4.3.1.1 Each Reactor Trip System instrumentation channel and interlock and the automatic trip logic shall be demonstrated OPERABLE by the performance of the Reactor Trip System Instrumentation Surveillance Requirements specified in Table 4.3 1, 4.3.1.2 The REACTOR TRIP SYSTEM RESPONSE TIME of each Reactor trip function r
shall be demonstrated to be within its limit at least once per 18 months.
Each test shall include at least one train such that both trains are tested at least once per 36 months and one channel (to include input relays to both trains) per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific Reactor trip function as shown in the " Total No. of Channels" column of Table 3.3 1.
MILLSTONE - UNIT 3 3/4 3 1 Amendment No. 45 h
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TABLE 3.3-1 xp REACTOR TRIP SYSTEM INSTRUMENTATION 0;
-g MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICA8LE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE NODES ACTION b
1.
1 2
1, 2 1
2 1
2 3*, 4*, 5*
11 w
2.
Power Range, Neutron Flux a.
High Setpoint 4
2 3
1, 2 2#
b.
Low Setpoint 4
2
.3 1###, 2 2#
3.
Power Range, Neutron Flux 4
2 3
1, 2 2#
High Positive Rate 4.
Power Range, Neutron Flux, 4
2 3
1, 2 2#
High Negative Rate w
N 5.
Intermediate Range, Neutron Flux 2
1 2
18##, 2 3
j 6.
Source Range, Neutron Flux a.
Startup 2
1 2
2##
4 l
b.
Shutdown 2
0 1
3,4,5 5'
c.
Shutdown 2
1 2
3*, 4*, 5*
11 7.
Overtemperature AT l
a.
Four Loop Operation 4
2 3
1, 2 6#
t i
b.
Three Loop Operation 3
2 2
1, 2 68 8.
Overpower AT a.
Four Loop Operation 4
2 3
1, 2 6#
1 b.
Three Loop Operation 3
2 2
1, 2 6#
9.
Pressurizer Pressure--Low 4
2 3
1**
6# (1) 10.
Pressurizer Pressure--High 4
2 3
1, 2 6# (1) 11.
Pressurizer Water Level--High 3
2 2
1**
6#
1 l
INSTRUMENTATION i
3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTA LIMITING CONDITION FOR OPERATION 3.3.2 The Engineered Safety Features Actuation System (ESFAS) instrumentation
+
channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their Trip Setpoints set consistent with the values shown in the Trip Setpoint column of i
Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5.
l APPLICABILITY:
As shown in Table 3.3-3.
ACTION:
With an ESFAS Instrumentation or Interlock Trip Setpoint trip less a.
conservative than the value shown in the Trip Setpoint column but more conservative than the value shown in the Allowable Value column of Table 3.3-4, adjust the Setpoint consistent with the Trip Setpoint
- value, b.
With an ESFAS Instrumentation or Interlock Trip Setpoint less conserva-tive than the value shown in the Allowable Value column of Table 3.3-4, either:
1.
Adjust the Setpoint consistent with the Trip Setpoint value of Table 3.3-4, and determine within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that Equation 2.2-1 t
was satisfied for the affected channel, or 2.
Declare the channel inoperable and apply the applicable ACTION statement requirements ^f Table 3.3-3 until the channel is restored to OPERABLE status with its Setpoint adjusted consistent with the Trip Setpoint value.
Equation 2.2-1 2 + R + S 5, TA Where:
Z = The value from Column 2 of Table 3.3-4 for the affected channel, R = The "as measured" value (in percent span) of rack error for the affected channel, S = Either the "as measured" value (in percent span) of the sensor error, or the value from Column 5 (Sensor Error) of Table 3.3-4 for the affected channel, and TA = The value from Column TA (Total Allowance) of Table 3.3-4 for the affected channel.
With an ESFAS instrumentation channel or interlock inoperable, take c.
the ACTION shown in Table 3.3-3.
I MILLSTONE - UNIT 3 3/4 3-15
INSTRUMENTATION SURVEILLANCE REOUIREMENTS 4.3.2.1 Each ESFAS instrumentation channel and interlock and the automatic actuation logic and relays shall be demonstrated OPERABLE by performance of the ESFAS Instrumentation Surveillance Requirements specified in Table 4.3 2.
4.3.2.2 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 18 months.
Each test shall include at least one train such that both trains are tested at least once per 36 months and one channel (to include input relays to both trains) per function such that all channels are tested at least once per N.
times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the " Total No. of Channels" column of Table 3.3 3.
MILLSTONE - UNIT 3 3/4 3-16 Amendment No. 45 e
fm 5
- p TABLE 4.3-2 (Continued) m.
N ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTiUENTATION SURVEILLANCE REQUIREMENTS E
TRIP G
ANALOG ACTUATING MODES CHANNEL DEVICE M4 STER SLAVE FOR WHICH 1
m CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST TEE IIS.T IS REQUIRED
- a. Manual Initiation N.A.
N.A.
N.A.
R N.A.
N.A.
N.A.
1, 2, 3
- b. Automatic Actuation N.A.
M.A N.A.
M.A.
M(1)
M(I)
Q 1, 2, 3 and Actuation Relays
- c. Steam Generator Water S
R M
N.A.
H.A.
N.A N.A 1, 2, 3
{
Level-Low-Low Y
- d. Safety Injection See Item I. above for all Safety Injection Surveillance Requirements.
4
- e. Loss-of-Offsite Power See Item 8 below for all Loss of Power Surveillance Requirements.
- f. Containment Depres-See Item 2. above for all CDA Surveillance Requirements.
surization Actuation (CDA)
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7.
Control Building Isolation l
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- a. Manual Actuation M.A.
N.A.
N.A.
R N.A.
N.A.
N.A.
All
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- b. Manual Safety N.A.
N.A.
N.A.
R N.A.
N.A.
N.A.
I,2,3,4 Injection Actuation
- c. Automatic Actuation M.A.
N.A.
N.A.
N.A.
M(1)
M(I)
Q I, 2, 3, 4 m
logic and Actuation Relays
- d. Containment Pressure--
S R
M N.A.
M.A.
N.A.
N.A.
1, 2, 3 High-1 n
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l TABLE 4.3-2 (Continued) h ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUE NTATION-0; SURVEILLANCE REQUIREMENTS
$g TRIP ANALOG ACTUATING MODES CHANNEL DEVICE MASTER SLAVE FOR NMICH c5 CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE
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FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST J111 1L31 IS REOUINED
- 7. Control Building Isolation (Continued)
- e. Control Building Inlet S
R M
N.A.
N.A.
N.A.
N.A.
All Ventilation Radiation
- 8. Loss of Power
- a. 4 kV Bus N.A.
R N.A M(3)
N.A.
N.A.
N.A.
1, 2, 3, 4 i
Undervoltage (Loss
,t*
of Voltage)
[
- b. 4 kY Bus N.A.
R N.A.
M(3)
N.A.
N.A.
N.A.
I, 2, 3, 4 1
Undtrvoltage (Grid Degraded Voltage) o t
- 9. Engineered Safety Features Actuation System Interlocks
- a. Pressurizer M.A.
R H
N.A.
M.A.
N.A.
N.A.
1, 2, 3 Pressure, P-II l
- b. Low-Low Tavg, P-12 N.A.
R M
N.A.
N.A.
N.A.
N.A.
1, 2, 3 yg
- c. Reactor Trip, P-4 N.A.
N.A.
N.A.
R N.A.
N.A.
M.A.
1, 2, 3 h
- d. Steam Generator 5
R
- M N.A.
M(1)
M(1)
Q 1, 2, 3 -
g Water Level, P-14 o
g
- 10. Emergency Generator N.A.
N.A.
N.A.
N.A.
Q(1,2)
N.A.
N.A.
I, 2, 3, 4 Load Sequencer (J1 e
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TABLE 4.3-2 (Continued)
TABLE NOTATION (1) Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.
(2) This surveillance may be performed continuously by the emergency generator load sequencer auto test system as long at the EGLS auto test system is demonstrated operable by the performance of an 3
ACTUATION LOGIC TEST at least once per 92 days.
(3) On a monthly basis an undervoltago condition will be initiated at the sensing device to verify the operability of the trip actuating device arid verify that the associated logic and alarm relays operate.
B MILLSTONE UNIT 3 3/4 3-41 Amendment No. 45 e.
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