ML17329A336
| ML17329A336 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/05/1991 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17329A337 | List: |
| References | |
| NUDOCS 9112240243 | |
| Download: ML17329A336 (20) | |
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. I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
160 License No. DPR-58 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
B.
The application for amendment by Indiana Michigan Power Company (the licensee) dated April 16, 1991, 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; 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 P'art 51 of the Commission's regulations and all applicable requirements have been satisfied.
9ii224024S Pii205 PDR ADOCII; 050003i5 p
2.
Accordingly, the license is amended by changing paragraph 2.C.(2) of Facility Operating License No. DPR-58 is hereby amended to read as follows:
The Technical Specifications contained in Appendices A
and B, as revised through Amendment No. 16O 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 L. B. Marsh, Director Project Directorate III-I Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation Date of Issuance:
December 5, iggi
ATTACHMENT TO LICENSE AMENDYIENT NO.
FACILITY OPERATING LICENSE NO. DPR-58 DOCKET NO. 50-315 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.
RENOVE 1-2 3/4 6-1 3/4 6-3 3/4 6-4 3/4 6-5
- 3/4 6-6 INSERT 1-2 3/4 6-1 3/4 6-3 3/4 6-4 3/4 6-5
- 3/4 6-6
- Over leaf page provided to maintain document completeness.
No changes contained on this page.
DEFINITIONS REPORTABLE EVENT 1.7 REPORTABLE EVENT shall be any of those conditions specified in 10 CFR 50.73.
CONTAINMENT INTEGRITY 1.8 CONTAINMENT INTEGRITY shall exist when:
1.8.1 All penetrations required to be closed during accident conditions are either:
a.
Capable of being closed by an OPERABLE containment auto>>
matic isolation v'alve system, or
- b. Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except as provided in Table 3.6-1 of Specification 3.6.3.1.
1.8.2 All equipment hatches are closed and sealed.
1.8.3 Each air lock is in compliance with the requirements of Specification 3.6.1.3, and 1.8.4 The containment leakage rates are within the limits of Specification 3.6.1.2.
CHANNEL CALIBRATION 1.9 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors.
The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST.
The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.
CHANNEL CHECK 1.10 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation.
This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.
COOK NUCLEAR PLANT - UNIT 1 1-2 AMENDMENT NO. 87)
3 4.6 CONTAINMENT SYSTEMS 3 4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE RE UIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
a \\
At least once per 31 days by verifying that:
1.
All penetrations* not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Table 3.6-1 of Specification 3.6.3.1, and 2.
All equipment hatches are closed and sealed, By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3.
- Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed or otherwise secured in the closed position.
These penetr.": Lons shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.
COOK NUCLEAR PLANT - UNIT 1 3/4 6-1 AMENDMENT NO. gg, ]gp
CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS b.
If any periodic Type A test fails to meet
.75 L, the test a'chedule for subsequent Type A tests shall be reviewed and approved by the Commission.
If two consecutive Type A tests fail to meet
.75 L,
a Type A test shall be performed at least every ls months until two consecutive Type A tests meet
.75 L, at which a'ime the above test schedule may be resumed.
C ~
The accuracy of each Type A test shall be verified by a supplemental test which:
1.
Confirms the accuracy of the Type A test by verifying that.
the difference between supplemental and Type A test data is within 0.25 L
a'.
Has a duration sufficient to establish accurately the change in leakage between the Type A test and the supplemental test.
3.
Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be equivalent to at least 25 percent of the total measured leakage rate at P
, 12.0 psig.
a'
~
Type B and C tests shall be conducted at P
, 12.0 psig, at a'ntervals no greater than 24 months except for tests involving ai r locks.
e.
Each containment air lock shall be verified to be in compliance with the requirements of Specification 3. 6. 1. 3.
f.
All test leakage rates shall be calculated using observed data converted to absolute values.
Error analyses shall be performed to select a balanced integrated leakage measurement system.
COOK NUCLEAR PLANT - UNIT 1 3/4 6-3 AMENDMENT NP. l6p'
0
.t L
CONTAINMENT SYSTEMS CONTAINMENT AIR LOCKS LIMITING CONDITION FOR OPERATION 3.6.1.3 Each containment air lock shall be OPERABLE with:
a.
Both doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closed, and b.
An overall air lock leakage rate of less than or equal to 0.05 La at P
12 psig.
a'PPLICABILITY:MODES 1, 2,
3 and 4.
ACTION:
With an air lock inoperable, restore the air lock to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE RE UIREMENTS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:
- After each opening, except when the air lock is being used for multiple entries, when it shall be done at least once per 3 days, by performing an air leakage test without a simulated pressure force on the door by pressurizing the gap between the seals to 12 psig and verifying a seal leakage of no greater than 0 '
L a
1
- Exemption to Appendix "J" of 10 CFR 50.
COOK NUCLEAR PLANT - UNIT 1 3/4 6-4 AMENDMENT NO.
160
CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS Continued b.
co At least once per 6 months, perform an air leakage test without a simulated pressure force on the door per 4.6.1.3.a.,
then perform an air leakage test with a simulated pressure force on the door, by pressurizing the gap between the seals to 12 psig and verifying a seal leakage of no greater than 0.0005 L.
a't least once per 6 months by conducting an overall air lock leakage test at P
(12 psig) and by verifying that the overall air lock leakage rate is within its limit.
At least once per 6 months by verifying that only one door in each air lock can be opened at a time.
COOK NUCLEAR PLANT - UNIT 1 3/4 6-5 AMENDMENT NQ.
160
CONTAINMENT SYSTEMS INTERNAL PRESSURE LIMITING CONDITION FOR OPERATION 3.6.1.4 Primary containment internal pressure shall be maintained between -1.5 and +0.3 psig.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With the containment internal pressure outside of the limits above, restore the internal pressure to within the limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.1.4 The primary containment internal oressure shall be determined to within the limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D. C.
COOK-UNIT 1
3/4 6-6
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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.
144 License No. DPR-74 The Nuclear Regulatory Commission (the Commission) has.found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated April 16,
- 1991, 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 2.
Accordingly, the license is amended by changing paragraph 2.C.(2) of Facility Operating License No. DPR-74 is hereby amended to read as fol1ows:
The Technical Specifications contained in Appendices A
and B, as revised through Amendment No. i44are 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 L. B. Marsh, Director Project Directorate III-1 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation Date of Issuance:
December 5, i99i
ATTACHMENT TO LICENSE AMENDMENT NO.
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'umber and contain marginal lines indicating the area of change.
REMOVE 1-2 3/4 6-1
- 3/4 6-2 3/4 6-3 INSERT 1-2 3/4 6-1
- 3/4 6-2 3/4 6-3
- Overleaf page provided to maintain document completeness.
No changes contained on this page.
J 4
l>>
I'l
DEFINITIONS REPORTABLE EVENT 1.7 A REPORTABLE EVENT shall be any of those conditions specified in 10 CFR 50.73.
CONTAINMENT INTEGRITY 1.8 CONTAINMENT INTEGRITY shall exist when:
1.8.1 All penetrations required to be closed during accident conditions are either:
a.
Capable of being closed by an OPERABLE containment automatic isolation valve system, or b.
Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except as provided in Table 3.6-1 of Specification 3.6.3.1.
- 1. 8. 2 All equipment hatches are closed and sealed, 1.8.3 Each air lock is in compliance with the requirements of Specification 3.6.1.3, 1.8.4 The containment leakage rates are within the limits of Specification 3.6.1.2, and 1.8.5 The sealing mechanism associated with each penetration (e.g.,
welds, bellows or 0-rings) is OPERABLE.
CHANNEL CALIBRATION 1.9 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors.
The CHANNEL CALZBRATZON shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST.
The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.
CHANNEL CHECK 1.10 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation.
This determination shall include, where
- possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.
COOK NUCLEAR PLANT - UNIT 2 1-2 AMENDMENT NO yg
>44
3 4.6 CONTAINMENT SYSTEMS 3 4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAZNMENT INTEGRITY shall be maintained.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
'a ~
At least once per 31 days by verifying that:
1.'ll penetrations*
not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Table 3.6-1 of Specification 3.6.3.1, and 2.
All equipment hatches are closed and sealed, b.
By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3.
+Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed or otherwise secured in the closed position.
These penetrations shall be verified closed during eac';.
COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.
COOK NUCLEAR PLANT - UNIT 2 3/4 6-1 AMENDMENT NO. ]44
CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of <
L, 0.25 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P
12 psig.
b.
A combined leakage rate of < 0.60 L for all penetrations and valves subject to Type B and C test3, when pressurized to P
a APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L, or (b) with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 L
, restore the overall integrated leakage rate to
< 0.75 L
and the coSbined leakage rate for all penetrations and valves subjec$
to Type B and C tests to
< 0.60 L
prior to increasing the Peactor Coolant System temperature above 500'F.
SURVEILLANCE RE UIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972:
a.
Three Type A test; (Overall Integrated Containment Leakage Rate) shall be conducted at 40 + 10 month intervals during shutdown ;;
P 12 psig, during each 10-year service period.
The third test of each set shall be conducted during the shutdown for the 10-year plant inservice inspection.
0.
C.
COOK - UNIT 2 3/4 6-2
S CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS Continued b.
If any periodic Type A test fails to meet
.75 L, the test a
schedule for subsequent Type A tests shall be reviewed and approved by the Commission.
If two consecutive Type A tests fail to meet
.75 L,
a Type A test shall be performed at least every 18 months until two consecutive Type A tests meet
.75 L, at which time the above test schedule may be resumed.
a'.
The accuracy of each Type A test shall be verified by a supple-mental test which:
1.
Confirms the accuracy of the Type A test by verifying that the difference between supplemental and Type A test data is within 0.25 L, a'.
Has a duration sufficient to establish accurately the change in leakage between the Type A test and the supplemental test.
3.
Requires the quantity of gas injected into the contain-ment or bled from the containment during the supplemental test to be equivalent to at least 25 percent of the total measured leakage rate at P, 12.0 psig.
a'.
Type B and C tests shall be conducted at P
, 12.0 psig, at a'ntervals no greater than 24 months except for tests involving air locks.
e.
Each containment air lock shall be verified to be in compliance with the requirements of Specification 3.6.1.3.
- f. All test leakage rates shall be calculated using observed data converted to absolute values.
Error analyses shall be performed to select a balanced integrated leakage measurement system.
g.
The provisions of Specification 4.0.2 are not applicable.
COOK NUCLEAR PLANT - UNIT 2 3/4 6-3 AMENDMENT NO.
~ 44
'I