ML20216J872
| ML20216J872 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 09/10/1997 |
| From: | Stang J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20216J876 | List: |
| References | |
| NUDOCS 9709180134 | |
| Download: ML20216J872 (8) | |
Text
.
44 y-UNITED STATES
,[
NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. some64cm
'+,,.....,o COMMONWEALTH EDISCN COMPANY DOCKET NO. 50-2H DRESDEN NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.162 License No. OPR-19 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Comonwealth Edison Company (the licensee) dated January 24, 1997, 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 Comission; 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 Comission'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. DPR-19 is hereby amended to read as follows:
9709190134 970910 DR ADOCK 0500 7
. (2)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.162, 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 and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION W
4 +.
J n F. Stang, nior Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications
-Date of Issuance: September 10, 1997
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UNITED STATES y-
)
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 3006M001 s,...../
COMMONWEALTH EDISON COMPANY DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.157 License No. DPR-25 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Comonwealth Edison Company (the licensee) dated January 24, 1997, 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 Comission; 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 conducted in compliance with the Comission's regulations; D.
The. issuance of this amendment will not be inimical to the common defense and security or to the health and spety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission'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 3.B. of Facility Operating License No. DPR-25 is hereby amended to read as follows:
l l
i m
. B.
Technical Soeejfications The Technical Specifications contained in Appendix A, as revised through Amendment No.157, are hereby incorporated in-the license. The licensee shall oper.ite the facility in accordance with the Technical Specifications.
3.
This license emendment is effective as of the date of its issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION Join F. Stang, Se ior Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date-of Issuance: September 10, 1997
I ATTACHMENT TO LICENSE AMENDMENT NOS 162AND 157 FACILITY OPERATING LICENSE NOS. DPR-19 AND DPR -25 DOCKET NOS. 50-237 AND 50-249 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3/4.2-18 3/4.2-18 3/4.2-19
.3/4.2-19 3/4.2-20 3/4.2-20 L
-a m
m v
w
TABLE 4.2.8-1 ECCS ACTUATION INSTRUMENTATION O
SURVEILLANCE REQUIREMENTS m
m IG; m
a n
M CHANNEL Applicable C
Z CHANNEL FUNCTIONAL CHANNEL OPERATIONAL k c-Functional Unit CHECK TEST CAllBRATION MODEis) z y
4-L CORE SPRAY (CS) SYSTEM d
m o
to z
g.
.l a.
Reactor Vessel Water Level - Low Low S
M E*
1,2,3,4",5" b.
Drywell Pressure - High" NA M
Q 1,2,3 c.
Reactor Vessel Pressure - Low (Permissive)
NA M
Q 1,2,3,4",5" d.
CS Pump Discharge Flow - Low (Bypass)
NA Q
E" 1,2,3,4",5" 2
LOW PRESSURE COOLANT INJECTION (LPCI) SUBSYSTEM j
l a.
Reactor Vessel Water Level - Low Low S
M E*
1,2,3,4",5" w
A b.
Drywell Pressure - High*
NA M
Q 1,2,3 m
c.
Reactor Vessel Pressure - Low (Permissive)
NA M
Q 1,2,3,4",5" d.
LPCI Pump Discharge Flow - Low (Bypass)
NA O
E*
1,2,3,4",5" 1 HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEMS l
a.
Reactor Vessel Water Lovel - Low Low S
M E"'
1,2,3 l
g-b.
Drywell Pressure - High" NA M
Q 1,2,3 m.
o g
c.
Condensate Storage Tank Level - Low NA M
NA 1,2,3 g
d.
Suppression Chamber Water Level - High NA M
NA 1,2,3
{
~
l e.
Reactor Vessel Water Level - High (Trip)
NA M
E*
1,2,3
(
zo E
f.
HPCI Pump Discharge Flow - Low (Bypass)
NA Q
Q 1,2,3 0
os f
g.
Manual Initiation NA E
NA 1,2,3 5
m.
.v
?
TABLE 4.2.B-1 (Continued)
~
ECCS ACTUATION INSTRUMENTATION'
.O-SURVEILLANCE REQUIREMENTS :
- n g
- 4 0=
t m
Z CHANNEL'. -
Applicable.
CHANNEL ~
^ FUNCTIONAL.
' CHANNEL"
.. OPERATIONAL 1
.c, Ct!fGK TEST.
CAUBRATION MODE (s)
'i!E
- Functional Unit -
= -4
.m-
& AUTOMATIC DEPRESSURIZATION SYSTEM W
g ll La. Reactor Vessel Water Level - Low Low S'
M E"
1,2,3~
l b.
Drywell Pressere - High" NA M
Q 1,2,3 c.
Initiation Timer' NA E
'E 1,2,3 f
' d.
Low Low Level Timer NA
.E E-1,2,3
.e.-
CS Pump Discharge Pressure - High NA M'
O 1,2,3'
-l
-a (Permissive) 3 f.
LPCI Pump Discharge Pressure - High NA M
Q
- 1, 2; 3 '
[
w g
. (Permissive)
[
^
L LOSS OF POWER a.
4.16 kv Emergency Bus Undervoltage NA E
E 1,2,3,4*,5* -
l (Loss of Voltage) i 1
b.
4.16 kv Emergency Bus Undervoltage NA' E
E 1,2,3,4*,5"
_t (Degraded Voltage) l
.3 m
a o
U n
k 3
W-e t
-3 g
-f^
8 C
.u.
g 5
l
>.4
INSTRUMENTATION ECCS Actuation 3/4.2.8 TABLE 4.2.B 1 (Continued)
)
ECCS ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS TABLE NOTATIOtj (a) Not required to be OPERABLE when reactor steam dome pressure is s150 psig.
(b) When the system is required to be OPERABLE per Specification 3.5.B.
(c) Required when the associated diesel generator is required to be OPERABLE per Specification 3.9.B.
(d) T;ils function is not required to be OPERABLE when PRIMARY CONTAINMENT INTEGRITY is not required.
(e) Trip units are calibrated at least once per 92 days and transmitters are calibrated at the frequency identified in the table.
(f) Trip units are calibrated at leest once per 92 days and transmitters are calibrated at the frequency indentified in the table.
DRESDEN - UNITS 2 & 3 3/4.2-20 Amendment Nos.162 and 157