ML17328A056
| ML17328A056 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/05/1989 |
| From: | Yandell L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17328A057 | List: |
| References | |
| NUDOCS 8907110434 | |
| Download: ML17328A056 (24) | |
Text
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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.
127 License No. DPR-58 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated March 4, 1988, 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.
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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.
DPR-58 is hereby amended to read as follows:
Technical S ecifications The Technical Specifications contained in Appendices A and B,
's revised through Amendment No.
127
, 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 REGU TORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 5, 1989 8
Lawrence A. Yandell, Acting irector Project Directorate III-1 Division of Reactor Projects - III, IV, V 8 Special Projects Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NO.
127 TO FACILITY OPERATING LICENSE NO.
DPR-58 DOCKET NO.
50-315 Revise Appendix A Technical Specifications by removing the pages identified below and insertin'g the attached pages.
The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
REMOVE 3/4 3-43 3/4 3-44 3/4 3-45 3/4 3"46 8 3/4 3-2 5-9 UNIT 1 INSERT 3/4 3-43" 3/4 3-44 3/4 3-45 3/4 3"46" B 3/4 3-2 5"9
- Overleaf page provided to maintain document completeness.
No change contained on this page.
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INSTRUMENTATION METEOROLOGICAL INSTRUMENTATION'IMITING CONDITION FOR OPERATION 3.3.3.4 The meteorological monitoring instrumentation channels shown in Table 3,3-8 shall be OPERABLE.
APPLICABILITY: At all times.
ACTION'.
Pith the number of'PERABLE meteorological monitoring channels less than requiredby Table 3.3-&, suspend all release of gaseous radioactive material from the radwaste gas decay tanks until the inoperable channel(s) is restored to OPERABLE status.
With one or more required meteorological monitoring channels inoperable for more than 7 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel(s) to OPERABLE status.
C.
The provisions of Specifications 3.0.3 and 3.0,4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.3.3.4 Each of the above meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-5.
D.
C.
COOK - UNIT 1 3/4 3-43
TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION INSTRUMENT LOCATION INSTRUMENT MINIMUM MINIMUM ACCURACY OPERABLE 1.
WIND SPEED
- a. Primary or Backup Meteorological Tower, Nominal Elev.
10 m
(1),(2)
Any 1/3 channels
- b. Primary Meteorological Tower, Nominal Elev.
60 m
(1),(2) 2.
WIND DIRECTION
- a. Primary or Backup Meteorological Tower, Nominal Elev, 10 m
+ 5 Any 1/3 channels
- b. Primary Meteorological Tower, Nominal Elev.
60 m
+ 5 3.
AIR TEMPERATURE (for 60 m to 10 m delta T)
- a. Primary Meteorological Tower, Nominal Elev.
10 m
- b. Primary Meteorological Tower, Nominal Elev, 60 m
+ 0.15 F
+ 0.15 F
NA (1) Starting speed of anemometer shall be < 1 mph.
(2) +
1% or 0.5 mph, whichever is greater.
(3) With delta T information unavailable, sigma theta (standard devi'ation of the horizontal wind direction as determined from emergency procedures) is to be used for the determination of stability class.
D.
C.
COOK - UNIT 1 3/4 3-44 Amendment No. 227
TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS INSTRUMENT CHANNEL CHECK CHANNEL CALIBRATION 1.
WIND SPEED a.
Nominal Elev.
10 m
b.
Nominal Elev.
60 m
SA SA 2.
WIND DIRECTION-a.
Nominal Elev.
10 m
b.
Nominal Elev.
60 m
D SA SA 3.
AIR TEMPERATURE - DELTA T a.
Nominal Elev.
10 m
b.
Nominal Elev.
60 m
SA SA D.
C.
COOK - UNIT 1 3/4 3-45 Amendment No.
127
4j 4
INSTRUMENTATION REMOTE SHUTDOWN INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.5 The remote shutdown monitoring instrumentation channels shown in Table 3.3-9 shall be OPERABLE with readouts displayed external to the control room.
APPLICABILITY:
MODES 1, 2 and 3.
ACTION:
With the number of OPERABLE remote shutdown monitoring channels less than required by Table 3.3-9, either:
a.
Restore the inoperable channel to OPERABLE status within 30 days, or b.
Be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE RE UIREMENTS 4.3.3.5 Each remote shutdow'n monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-6.
D. C.
COOK-UNIT 1 3/4 3-46
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INSTRUMENTATION BASES 3 4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core.
3 4.3.3.3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to-safety; This capability is required to permit comparison of the measured response to that used in the design basis for the facility.
3 4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere.
This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public.
For the meteorological instrumentation, the required channel check consists of a qualitative assessment of channel behavior during operation by observation.
For the 10 m wind speed and wind direction instruments the channel check also includes, when possible, a
comparison of channel indications.
3 4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room, This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.
D.
C.
COOK - UNIT 1 B 3/4 3-2 Amendment No.
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C.
COOK NlICLEAR PLANT, UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
.113 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 March 4, 1988, 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. 113
, 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 COt1MISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 5, 1989 Lawrence A. Yandell, Acting Director Project Directorate III-1 Division of Reactor Projects - III, IV, V
& Special Projects Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NO.
TO FACILITY OPERATING LICENSE NO.
DPR-74 DOCKET NO. 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 UNIT 2 INSERT 3/4 3-40 3/4 3"41 B 3/4 3"2 5-9 3/4 3-40 3/4 3"41 B 3/4 3-2 8 3/4 3-2a 5"9
3-OR GC 0
0 IN QO~CT~IO INSTRUMENT MINIMUM MINIMUM
~CQ~
~OPERAB 1.
WIND SPEED
- a. Primary or Backup Meteorological Tower, Nominal Elev.
10 m
(l),(2)
Any 1/3 channels
- b. Primary Meteorological Tower, Nominal Elev.
60 m
(1) (2) 2.
WIND DIRECTION
- a. Primary or Backup Meteorological Tower, Nominal Elev.
10 m
5 Any 1/3 channels
- b. Primary Meteorological Tower, Nominal Elev.
60 m 5
3.
AIR TEMPERATURE (for 60 m to 10 m delta T)
- a. Primary Meteorological Tower, Nominal Elev.
10 m
- b. Primary Meteorological Tower, Nominal Elev.
60 m
+ 0.15 F
+ 0.15 F
(1) Starting speed of anemometer shall be < 1 mph.
(2) + 18 or 0.5 mph, whichever is greater.
(3) With delta T information unavailable, sigma theta (standard deviation of the horizontal wind direction as determined from emergency procedures) is to be used for the determination of stability class.
D.
C.
COOK - UNIT 2 3/4 3-40 Amendment No. NS>>333
TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS INSTRUMENT 1.
WIND SPEED CHANNEL CHECK CHANNEL CALIBRATION a.
Nominal Elev.
10 m
b.
Nominal Elev.
60 m
SA SA 2.
WIND DIRECTION.
a.
Nominal Elev.
10 m
b.
Nominal Elev.
60 m
SA SA 3.
AIR TEMPERATURE -
DELTA T a.
Nominal Elev.
10 m
b.
Nominal Elev.
60 m
SA SA D.
C.
COOK - UNIT 2 3/4 3-41 Amendment No.
RS >113
d 4'
.3 4.3.
INSTRUMENTATION BASES 3 4.3.3 MONITORING INSTRUMENTATION 3 4.3.3.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that 1) the radiation levels are continually measured in the areas served by the individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.
3 4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core.
The OPERABILITY of this system is demonstrated by irradiating each detector used and normalizing its respective output.
3 4.3.3.3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety.
This capability is required to permit comparison of the measured response to that used in the design basis for the facility.
3 4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive material to the'tmosphere.
This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public.
For the meteorological instrumentation, the required channel check consists of a qualitative assessment of channel behavior during operation by observation.
For the 10 m wind speed and wind direction instruments the channel check also
- includes, when possible, a comparison of channel indications.
3 4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room.
This capability if required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.
D.
C.
COOK - UNIT 2 B 3/4 3-2 Amendment No.
5g,g$,113
3 4.3 INSTRUMENTATIO E
BASES 3
4. 3. 3. 6 POST-ACCIDENT INSTRUMENTATION The OPERABILITY of the pose-accident instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables during and following an accident.
The containment water level and containment sump level transmitters will be modified or replaced and OPERABLE by the end of the outage currently scheduled to begin in May 1988.
D.
C.
COOK - UNIT 2 B 3/4 3-2a (Effective before start up following refueling outage currently scheduled in early 1988)
Amendment No. 113
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