ML17332A281
| ML17332A281 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/29/1994 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17332A282 | List: |
| References | |
| NUDOCS 9409070297 | |
| Download: ML17332A281 (18) | |
Text
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I tv j." I k**~4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
181 License No.
DPR-58 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
B.
C.
D.
E.
The application for amendment by Indiana Michigan Power Company (the licensee) dated September 24, 1992 as supplemented March 2,
- 1994, 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; 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; 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 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.
9409070297 940829 PDR ADOCK 05000315 P
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.
- 181, 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 issuance.
FOR THE NUCLEAR REGULATORY COMHISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 29, 1994 Ledyard B. Harsh, Director Project Directorate III-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
0 ATTACHMENT TO LICENSE AMENDMENT NO. 181 TO 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 vertical lines indicating the area of change.
REMOVE 1-2 3/4 6-1 3/4 6-14 3/4 6-15 3/4 6-16 3/4 6-17 3/4 6-18 3/4 6-19 3/4 6-20 3/4 6-21 3/4 6-22 B 3/4 6-3 INSERT 1-2 3/4 6-1 3/4 6-14 3/4 6-15 3/4 6-16 B 3/4 6-3
FINITIONS PO BE 1.7 A REPORTABLE EVENT shall be any of those conditions specified in 10 CFR 50.73.
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 contaixmmt automatic isolation valve system, or b.
Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except for valves that are open under administrative control as permitted by 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
'N C
0 1.9 A CHANNEL CALIBRATION shall be the ad)ustment, 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 QiL'INEL 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.
C EL CHECK 1.10 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation.
This determination shall include, ~here
- 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.~ 460-181
346 C
A S
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6 CO TING CO 0
0 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
~CT ON:
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 UIR ENTS 4.6.1
~ 1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
a 0
At least once per 31 days by verifying that:
l.
All penetrations'ot 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 for valves that are open under administrative control as permitted by Specification 3.6.3.1, and 2.
All equipment hatches are closed and sealeh.
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 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~ 440-181
ENT S
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V NG COND T 0 0
0 3 '.3.1 Each containment isolation valve shall be OPERABLE.
Containment purge valves and locked or sealed closed valves may be opened on an intermittent basis under administrative control.
The ACTION statement of T/S 3/4.6.3.1 is not applicable to the containment purge supply and exhaust isolation valves.
The Limiting Condition for Operation and its associated ACTION statement for these valves is given in Technical Specification 3/4.6.1.7.
~CT ON:
With one oz more of the containment isolation valve(s) inoperable, either:
a.
Restore the inoperable valve(s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or b.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or c.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange, or d.
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 />.
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.6.3.1.1 Each containment isolation valve shall be demonstrated OPERABLE prior I
to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated
- actuator, control or power circuit by performance of a cycling test and verification of isolation time.
COOK NUCLEAR PIANT - UNIT 1 3/4 6-14 AMENDMENT NO. 9S, 47Q 181
0 AINM S
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4.6.3.1.2 Each containment isolation valve shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:
a.
Verifying that on a Phase A containment isolation test signal, each Phase A isolation valve actuates to its isolation position.
b.
Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve actuates to its isolation position.
c.
Verifying that on a Containment Purge and Exhaust isolation signal, each Purge and Exhaust valve actuates to its isolation position.
4.6.3.1.3 The isolation time of each power operated or automatic containment isolation valve shall be determined to be within its limit when tested pursuant to Specification 4.0.5.
COOK NUCLEAR PIANT - UNIT 1 3/4 6-15 AMENDMENT NO. ~ 444 g68 181
Pages 3/4 6-17 through 3/4 6-22 deleted COOK NUCLEAR PLANT - Unit l 3/4 6-16 AMENDMENT NO.44-181
SY 3 4 RE S
ON C
46 CO The OPERABILITY of the containment spray system ensures that containment depressurization and cooling capability will be available in the event of a LOCA.
The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the accident analyses.
The OPERABILITY of the spray additive system ensures that sufficient NaOH is added to the containment spray in the event of a LOCA.
The limits on NaOH minimum volume and concentration, ensure that 1) the iodine removal efficiency of the spray water is maintained because of the increase in pH value, and 2) corrosion effects on components within containment are minimized.
These assumptions are consistent with the iodine removal efficiency assumed in the accident analyses.
3 4 6
3 CONTA SO 0
V VS The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment.
Containment isolation within the time limits specified ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.
The opening of containment purge and exhaust valves and locked or sealed closed containment isolation valves on an intermittent basis under administrative control includes the following considerations:
(1) stationing a qualified individual, who is in constant communication with control room, at the valve
- controls, (2) instructing this individual to close these valves in an accident situation, and (3) assuring that environmental conditions will not preclude access to close the valves and that this action will prevent the release of radioactivity outside the containment.
3 4 6 4 COMBUST B E
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The OPERABILITY of the equipment and systems required for the detection and control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions.
Either recombiner unit is capable of controlling the expected hydrogen generation associated with 1) zirconium-water reactions, 2) radiolytic decomposition of water and 3) corrosion of metals within containment.
COOK NUCLEAR PLANT - UNIT 1 B 3/4 6-3 AMENDMENT NO, 181
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4~*y4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205580001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 165 License No.
DPR-74 l.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
B.
C.
The application for amendment by Indiana Michigan Power Company (the licensee) dated September 24, 1992 as supplemented March 2,
- 1994, 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; 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.
165
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications'.
This license amendment is effective as of the date of issuance FOR THE NUCLEAR REGULATORY COMNISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 29, 1994 Ledyard B, Harsh, Director Project Directorate III-I Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NO. 165 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 vertical lines indicating the area of change.
REMOVE 1-2 3/4 6-1 3/4 6-13 3/4 6-14 3/4 6-15 3/4 6-16 3/4 6-17 3/4 6-18 3/4 6-19 3/4 6-20 3/4 6-21 3/4 6-22 3/4 6-23 3/4 6-24 3/4 6-25 3/4 6-26 3/4 6-27 3/4 6-28 3/4 6-29 3/4 6-30 3/4 6-31 3/4 6-32 B 3/4 6-3 INSERT 1-2 3/4 6-1 3/4 6-13 3/4 6-14 3/4 6-15 B 3/4 6-3
I ON EPORT B
1.7 A REPORTABLE EVENT shall be any of those conditions specified in 10 CFR 50.73.
CONTAINMENT INTEG 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 for valves that are open under administrative control as permitted by 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 CALIBRAT 0 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 CHEC 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.~~ 165
46 CO 4
6 CO 0
FOR 0E 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
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 />.
S V
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 for valves that are open under administrative control as permitted by Specification 3,6,3.1, and 2.
All equipment&atches 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 each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.
COOK NUCLEAR PIANT - UNIT 2 3/4 6-1 AMENDMENT~ 165
CONT NT S S
4 6
0 V
V L'IMI I G
COND T ON FOR 0 ON 3.6.3.1 Each containment isolation valve shall be OPERABLE.
Containment purge
~alves and locked or sealed closed valves may be opened on an intermittent basis under administrative control.
The ACTION statement of Technical Specification 3/4.6.3.1 is not applicable to the containment purge and exhaust isolation valves.
The Limiting Condition for Operation and its associated ACTION statement for these valves are given in Technical Specification 3/4.6.1.7.
~CTION:
With one or more of the containment isolation valve(s>
inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and either:
a.
Restore the inoperable valve(s) to OPERABLE status within 4
- hours, or b.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or c.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange; or d.
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 />.
The provisions of Specifications 3.0.4 are not applicable.
SURVEI LANCE E U R S
4.6.3.1.1 Each containment isolation valve shall be demonstrated OPERABLE prior I
to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated
- actuator, control or power circuit by performance of a cycling test and verification of isolation time.
COOK NUCLEAR PLANT - UNIT 2 3/4 6-13 AMENDMENT NO. 47, 453 165
CONTAINMENT SYSTEMS SURVEILLANCE RE UIREMENTS Continued 4.6.3. 1.2 Each containment isolation valve shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:f a.
Verifying that on a Phase A containment isolation test signal, each Phase A isolation valve actuates to its isolation position.
b.
Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve actuates to its isolation position.
c.
Verifying that on a Containment Purge and Exhaust isolation signal, each Purge and Exhaust valve actuates to its isolation position.
4.6.3. 1.3 The isolation time of each power operated or automatic containment isolation valve shall be determined to be within its limit when tested pursuant to Specification 4.0.5 t The provisions of Technical Specification 4.0.8 are applicable.
COOK NUCLEAR PLANT UNIT 2 3/4 6-14 AMENDMENT NO. 97., 43k
- 488, 165
Page 3/4 6-16 through 3/4 6-32 deleted COOK NUCLEAR PLANT - lJnit 2
3/4 6-15 AMENDMENT NO.
165
CO AT E
S 46 P
SS 00 G
CO The OPERABILITY of the containment spray system ensures that containment depressurization and cooling capability will be available in the event of a LOCA.
The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the accident analyses.
46'SP V
S T
The OPERABILITY of the spray additive system ensures that sufficient NaOH is added to the containment spray in the event of a LOCA.
The limits on NaOH voluae and concentration ensure a pH value of between 8.5 and 11.0 for the solution recirculated within containment after a LOCA.
This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.
These assumptions are consistent with the iodine removal efficiency assumed in the accident analyses.
The contained water volume limit includes an allowance for water not usable because of tank discharge location or other physical characteristics.
4 6
C 0
V V
The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment.
Containment isolation within the time limits specified ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.
The opening of containment purge and exhaust valves and locked or sealed closed containment isolation valves on an intermittent basis under administrative control includes the following considerations:
(1) stationing a qualified individual, who is in constant communication with control room, at the valve
- controls, (2) instructing this individual to close these valves in an accident situation, and (3) assuring that environmental conditions will not preclude access to close the valves and that this action will prevent the release of radioactivity outside the containment.
COOK NUCLEAR PLANT - UNIT 2 B 3/4 6-3 AHENDMENT NO~ 165