ML17325A819
| ML17325A819 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/15/1988 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Indiana Michigan Power Co |
| Shared Package | |
| ML17325A820 | List: |
| References | |
| DPR-58-A-117, DPR-74-A-103 NUDOCS 8806220358 | |
| Download: ML17325A819 (12) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.117 License No.
DPR-58 l.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated December 8, 1986, as supplemented August 7, 1987, 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 (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.
8806220358 8806l 5 PDR ADOCK 050003i 5 PDR
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-58 is hereby amended to read as follows:
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
1 17, 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.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance June 15'988 Daniel R. Muller, Acting Director Project Directorate III-1 Division of Reactor Projects - III, IV, V 6 Special Projects
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 1O>
License No.
DPR-74 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated December 8, 1986, as supplemented August 7, 1987, 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 (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.
DPR-74 is hereby amended to read as follows:
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 103
, 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.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 15r 1988 Daniel R. Muller, Acting Director Project Directorate III-1 Division of Reactor Projects - III, IV, V 8 Special Projects
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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO.
FACILITY OPERATING LICENSE NO.
DPR-58 AMENDMENT NO. "O~ FACILITY OPERATING LICENSE NO.
DPR-74 DOCKETS NOS.
50-315 AND 50-316 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
REMOVE 3/4 3-58 3/4 3"60 3/4 3-61 3/4 3-54 3/4 3-56 3/4 3-57 UNIT 1 UNIT 2 INSERT 3/4 3-58 3/4 3-60 3/4 3-61 3/4 3-54 3/4 3-56 3/4 3-57
t TABLE 3.3-12 D 0 CT VE I UID EFFLUE MONI ORING I S
UMENT TIO Instrument Minimum Channels O~ecable A licabilic
~caicn
- 1. Gross Radioactivity Monitors Providing Automatic Release Termination
- a. Liquid Radwaste Effluent Line (12-RRS-1001)
At times of release 23 b.
Steam Generator Blowdown Line (1-R-19)
At times of release 24 c.
Steam Generator Blowdown Treatment Effluent (1-R-24)
At times of release 24
- 2. Gross Radioactivity Monitors Not Providing Automatic Release Termination
- a. Service Water System Effluent Line (1-R-20, 1-R-28)
(1)per At all times train 25
- 3. Continuous Composite Sampler Flow Monitor
- a. Turbine Building Sump Effluent Line At all times 25 4.
Flow Rate Measurement Devices a, Liquid Radwaste Line(RFI-285)
- b. Discharge Pipes*
c.
Steam Generator Blowdown Treatment Effluent (1-DFI-352)
At times of release At all times At times of release 26 NA 26
- Pump curves and valve settings may be utilized to estimate flow; in such
- cases, Action Statement 26 is not applicable.
+ Monitor 1-R-18 may be used until. 12-RRS-1001 is declared OPERABLE following initial installation.
¹ OPERABILITY of 12-RRS-1001 includes OPERABILITY of flow switch RFS-1010, which is an attendant instrument as defined by Specification 1.6.
D.
Ce COOK - UNIT 1 3/4 3-58 Amendment No. gg, 3 17
TABLE 4.3-8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS INSTRUMENT 1.
Gross Beta or Gamma Radioactivity Monitors Providing Alarm and Automatic Isolation a.
Liquid Radwaste Effluent Line (12-RRS-1001) b.
Steam Generator Blowdown Effluent Line c.
Steam Generator Blowdown Treatment Effluent Line CHANNEL
~CHEC D*
SOURCE
~CHE g CHANNEL CALIBRA 0
R(3)
R(3)
R(3)
CHANNEL FUNCTIONAL TEST Q(5)
Q(1)
Q(1)
Gross Beta or Gamma Radioactivity Monitors Providing Alarm But Not Providing Automatic Isolation a.
Service Water System Effluent Line R(3)
Q(2) 3.
Continuous Composite Samplers a.
Turbin'e Building Sump Effluent Line 4.
Flow Rate Monitors a.
Liquid Radwaste Effluent b.
Steam Generator Blowdown Treatment Line D(4)*
D(4)*
N/A N/A N/A N/A N/A N/A
- During Releases Via This Pathway D. C.
Cook - Unit 1 3/4 3-60 Amendment No. gg, 117
TABLE 4.3-8 (Cont)
TABLE NOTATION (1)
The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:
- 2
- 3,
- %4.
Instrument indicates measured levels above the alarm/trip setpoint.
Circuit failure.*
Instrument indicates a downscale failure.*
Instrument control not set in operating mode.*
(2)
The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
l.
- 2
'k%3,
- 4
'nstrument indicates measured levels above the alarm setpoint.
Circuit failures Instrument indicates a downscale failure.
Instrument controls not set in operating mode.
(3)
The initial CHANNEL CALIBRATION shall be performed using one or more sources with traceability back to the National Bureau of Standards.
These sources shall permit calibrating the system over its intended range of energy and measurement range.
For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration may be used.
(4)
CHANNEL CHECK shall consist of verifying indication of flow during periods of release.
CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic or batch releases are made.
(5)
The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:
4%2 ~
4+3,
- 4.
4+5.
Instrument indicates measured levels above the alarm/trip setpoint.
Circuit failure.~
Instrument indicates a downscale failure.*++
Instrument control not set in operating mode.*
Loss of sample flow.
Instrument indicates, but does not provide for automatic isolation.
As equipment becomes operational.
- Instrument indicates, but does not necessarily cause automatic isolation; however, no credit is taken for automatic isolation on such occurrences.
D.
C.
COOK - UNIT 1 3/4 3-61 Amendment No, gg, A/7
D 0 C IVE LI UID EFFLUENT 0 I OR G I STRUMENTATION nstrument Minimum Channels
~Oerab le 1 cabilit Action
- 1. Gross Radioactivity Monitors Providing Automatic Release Termination
- a. Liquid Radwaste Effluent Line (12-RRS-1001)+
At times of release 23 b.
Steam Generator Blowdown Line (2-R-19)
At times of release 24 c.
Steam Generator Blowdown Treatment Effluent (2-R-24)
At times of release 24
- 2. Gross Radioactivity Monitors Not Providing Automatic Release Termination
- a. Service Mater System Effluent Line (2-R-20, 2-R-28)
- 3. Continuous Composite Sampler Flow Monitor (1) per At all times train 25
- a. Turbine Building Sump Effluent Line At all times 25
- 4. Flow Rate Measurement Devices
- a. Liquid Radwaste Line(RFI-285) b. Discharge Pipes*
c.
Steam Generator Blowdown Treatment Effluent (2-DFI-352)
At times of release At all times At times of release 26 NA 26
- Pump curves and valve settings may be utilized to estimate flow; in such
- cases, Action Statement 26 is not applicable.
+ Monitor 2-R-18 may be used until 12-RRS-1001 is declared OPERABLE" following initial installation.
0 OPERABILITY of 12-RRS-1001 includes OPERABILITY of flow s~itch RFS-1010, which is an attendant instrument as defined by Specification 1.6.
D. C.
COOK UNIT 2 3/4 3-54 Amendment No. gg 103
TABLE 4.3-8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS INSTRUMENT CHANNEL
~CHEC SOURCE CHECK CHANNEL CALIB TION CHANNEL FUNCTIONAL TEST 1.
Gross Beta or Gamma Radioactivity Monitors providing Alarm and Automatic Isolation a.
Liquid Radwaste Effluent Line (12-RRS-1001) b.
Steam Generator Blowdown Effluent Line c.
Steam Generator Blowdown Treatment Effluent Line D*
R(3)
R(3)
R(3)
Q(5)
Q(1)
Q(1) 2.
Gross Beta or Gamma Radioactivity Monitors Providing Alarm But Not Providing Automatic Isolation a.
Service Water System Effluent Line R(3)
Q(2) 3.
Continuous Composite Samplers a.
Turbine Building Sump Effluent Line 4.
Flow Rate Monitors a.
Liquid Radwaste Effluent b.
Steam Generator Blowdown Treatment Line D(4)*
D(4)*
N/A N/A N/A N/A N/A N/A N/A
- During Releases Via This Pathway D.
C.
Cook - Unit 2 3/4 3-56 Amendment No.
$g,
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TABLE 4.3-8 (Cont)
TABLE NOTATION (1)
The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:
- 2~
- 3~
- 4.
Instrument indicates measured levels above the alarm/trip setpoint.
Circuit failure.*
Instrument indicates a downscale failure.*
Instrument control not set in operating mode.*
(2)
The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
1.
- 2.
- 3
- 4.
Instrument indicates measured levels above the. alarm setpoint.
Circuit failure.
Instrument indicates a downscale failure.
Instrument controls not set in operating mode.
(3)
The initial CHANNEL CALIBRATION shall be performed using one or more sources with traceability back to the National Bureau of Standards.
These sources shall permit calibrating the system over its intended range of energy and measurement range.
For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration may be used.
(4)
CHANNEL CHECK shall consist of verifying indication of flow during periods of release.
CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic or batch releases are made.
(5)
The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:
- 2.
- 3
'*4.
- 5.
Instrument indicates measured levels above the alarm/trip setpoint.
Circuit failure.***
Instrument indicates a downscale failure.***
Instrument control not set in operating mode
- Loss of sample flow.
Instrument indicates, but does not provide for automatic isolation.
As equipment becomes operational.
- Instrument indicates, but does not necessarily cause automatic isolation; however, no credit is taken for automatic isolation on such occurrences.
D. C.
COOK - UNIT 2 3/4 3-57 Amendment No.
$7, gpss