ML17332A383
| ML17332A383 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/08/1994 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17332A385 | List: |
| References | |
| NUDOCS 9411140205 | |
| Download: ML17332A383 (15) | |
Text
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4 y**4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 185 License No.
DPR-58 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
B.
C.
D.
The application for amendment by Indiana Michigan Power Company (the licensee) dated December 22,
- 1993, 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 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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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 ecificat o
s The Technical Specifications contained in Appendices A and B,
as revised through Amendment No.
iB5, are hereby incor'porated 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 COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 8, 1994 John N. Hannon, Director Project Directorate III-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NO.
5 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 3/4 7-10 8 3/4 7-3 INSERT 3/4 7-10 8 3/4 7-3 8 3/4 7-3a
SY S
E 0
0 V
VES G
0 0
3.7.1.5 Each steam generator stop valve shall be OPERABLE.
MODES 1, 2 and 3.
hG~O MODE 1 With one steam generator stop valve inoperable but
- open, POWER OPERATION may continue provided the inoperable valve is restored to OPERABLE status wittiin 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; otherwise, reduce power to less than or equal to 5 percent of RATED THERMAL POWER within the next 6
hours.
MODES 2
and 3
With one or more steam generator stop valves inoperable, close the inoperable valve(s) within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and verify the inoperable valves are closed at least once per 7 days.
Otherwise, be in at least MODE 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, with the unit in at least MODE 3 within the first 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
The provisions'f Specification 3.0.4 are not applicable.
V LANC RE UI EME S
4.7.1.5.1 Each steam generator stop valve that is open shall be demonstrated OPERABLE by verifying full closure within 8 seconds when tested pursuant to Specification 4.0.5.
4.7.1.5.2 The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.
4.7.1.5.3 The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 when performing PHYSICS TESTS at the beginning of a cycle provided the steam generator stop valves are maintained closed.
COOK NUCLEAR PLANT - UNIT 1 3/4 7-10 AMENDMENT NO. 4&i, 447, 464 185
~S 'S CONDENS E STO GE The OPERABILITY of the condensate storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> with steam discharge to the atmosphere concurrent with total loss of off-site power.
4 4
CTV The limitations on secondary system specific activity ensure that the resultant off-site radiation dose willbe limited to a small fraction of 10 CEL Part 100 limits in the event of a steam line rupture.
This dose also includes the effects of a coincident 1.0 gpm primary to secondary tube leak in the steam generator of the affected steam line.
These values are consistent with the assumptions used in the accident analyses.
3 4 5
STEAM GENERATOR STOP VALVES The OPERABILITY of the steam generator stop valves ensures that no more than one steam generator will blowdown in the event of a steam line rupture.
This restriction is required to 1) minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and 2) limit the pressure rise within containment in the event the steam line rupture occurs within containment.
The OPERABILITY of the steam generator stop valves within the closure times of the surveillance requirements are consistent with the assumptions used in the accident analyses.
With one steam generator stop valve inoperable in MODE 1, action must be taken to restore OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
Some repairs to the valves can be made with the unit hot.
The 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> completion. time is reasonable, considering the low probability of an accident occurring during this time period that would require a closure of the steam generator stop valves.
If the steam generator stop valve cannot be restored to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, the unit must be placed in a MODE in which the LCO does not apply.
To achieve this status, the unit must be placed in MODE 2 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and the MODES 2 and 3 action statement entered.
The completion times are reasonable, based on operating experience, to reach MODE 2 and to close the steam generator stop valves in an orderly manner and without challenging unit systems.
Since the steam generator stop valves are required to be OPERABLE in MODES 2 and 3, the inoperable valves may either be restored to OPERABLE status or closed.
When closed, the valves are already in the position required by the assumptions in the safety analysis.
The 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> completion time is consistent COOK NUCLEAR PLANT - UNIT 1 B 3/4 7-3 AMENDMENT NO. 08,
- 185,
S EMS 4
5 TO S
VALV S nued with the MODE 1 action statement requirement.
For inoperable steam generator stop valves that cannot be restored to OPERABLE status within the specified completion time, but are closed, the inoperable valves must be verified on a periodic basis to be closed.
This is necessary to ensure that the assumptions in the safety analysis remain valid.
The 7 day completion time is reasonable, based on engineering judgement, in view of steam generator stop valve status indications available in the control room, and other administrative controls, to ensure that these valves are in the closed position.
If in MODES 2 or 3 the steam generator stop valves cannot be restored to OPERABLE status or are not closed within the associated completion time, the unit must be placed in a MODE in which the LCO does not apply.
To achieve this
- status, the unit must be placed at least in MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in MODE 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The allowed completion times are reasonable, based on operating experience, to reach the required unit conditions from MODE 2
conditions in an orderly manner and without challenging unit systems.
COOK KJCLEAR PIANT - UNIT 1 B 3/4 7-3a AMENDMENT NO. 185,
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~0 0 y*y4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON) 0 C 2055MO01 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.i7O License No.
DPR-74 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 December 22, 1993, 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.
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.
170, 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 COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 8,
1994 John N. Hannon, Director Project Directorate III-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
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 number and contain vertical lines indicating the area of change.
REMOVE 3/4 7-10 8 3/4 7-3 INSERT 3/4 7-10 B 3/4 7-3 B 3/4 7-3a
0 0
VLVS G
0 T
0 ON 3.7.1.5 Each steam generator stop valve shall be OPERABLE.
MODES 1, 2 and 3.
hHZo>:
MODE 1-With one steam generator stop valve inoperable but
- open, POWER OPERATION may continue provided the inoperable valve is restored.to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; otherwise, reduce power to less than or equal to 5 percent of RATED THERMAL POWER within the next 6
hours.
MODES 2-and 3
With one or more steam generator stop valves inoperable, close the inoperable valve(s) within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and verify the inoperable valves are closed at least once per 7 days.
Otherwise, be in at least MODE 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, with the unit in at least MODE 3 within the first 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
The provisions of Specification 3.0.4 are not applicable.
VE LLANCE RE UIREMENTS 4.7.1.5.1 Each steam generator stop valve that is open shall be demonstrated OPERABLE by verifying full closure within 8 seconds when tested pursuant to Specification 4.0.5.
4.7.1.5.2 The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.
4.7.1.5.3 The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 when performing PHYSICS TESTS at the beginning of a cycle provided the steam generator stop valves are maintained closed.
COOK NUCLEAR PIANT - UNIT 2 3/4 7-10 AMENDMENT NO. SR, 43k, 170
t.
I 2'
3 CO S
E STORAGE The OPERABILITY of the condensate storage tank with the minimum water volume ensures that sufficient water is available to maintain the RCS at HOT STANDBY conditions for 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> with steam discharge to the atmosphere concurrent with total loss of off-site power.
The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.
4 4
V The limitations on secondary system specific activity ensure that the resultant off-site radiation dose will be limited to a small fraction of 10 CFR Part 100 limits in the event of a steam line rupture.
This dose also includes the effects of a coincident 1.0 gpm primary to secondary tube leak ia the steam generator of the affected steam line.
These values are consistent with the assumptions used in the accident analyses.
3 4 1
G NERA OR S 0 V
V S
The OPERABILITY of the steam generator stop valves ensures that no more than one steam generator will blowdown in the event of a steam line rupture.
This restriction is required to 1) minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and 2) limit the pressure rise within containment in the event the steam line rupture occurs within containment.
The OPERABILITY of the steam generator stop valves within the closure times of the surveillance 'requirements are consistent with the assumptions used in the accident analyses.
Pith one steam generator stop valve inoperable in MODE 1, action must be taken to restore OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
Some repairs to the valves can be made with the unit hot.
The 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> completion time is reasonable, considering the low probability of an accident occurring during this time period that would require a closure of the steam generator stop valves. If the steam generator stop valve cannot be restored to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, the unit must be placed in a MODE in which the LCO does not apply.
To achieve this status, the unit must be placed in MODE 2 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and the MODES 2 and 3 action statement entered.
The completion times are reasonable, based on operating experience, to reach MODE 2 and to close the steam generator stop valves in an orderly manner and without challenging unit systems.
COOK NUCLEAR PLANT - UNIT 2 B 3/4 7-3 AMENDMENT NO. W, 170
S T
S EAM ENE 0
STOP V V
o ued Since the steam generator stop valves are required to be OPERABLE in MODES 2 and 3, the inoperable valves may either be restored to OPERABLE status or closed.
When closed, the valves are already in the position required by the assumptions in the safety analysis.
The 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> completion time is consistent with the MODE 1 action statement requirement.
For inoperable steam generator stop valves that: cannot be restored to OPERABLE status within the specified completion time, but are closed, the inoperable valves must be verified on a periodic basis to be closed.
This is necessary to ensure that the assumptions in the safety analysis remain valid.
The 7 day completion time is reasonable, based on engineeriag
)udgement, in view of steam generator stop valve status indications avai1able in the control room, and other administrative controls, to ensure that these valves are in the closed position.
If in MODES 2 or 3 the steam generator stop valves cannot be restored to OPERABLE status or are not closed within the associated completion time, the unit must be placed in a MODE in which the LCO does not apply.
To achieve this
- status, the unit, must be placed at least in MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in MODE 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The allowed completion times are reasonable, based on operating experience, to reach the required unit conditions from MODE 2
conditions in an orderly manner and without challenging unit systems.
COOK NUCLEAR PLANT - UNIT 2 B 3/4 7-3a AMENDMENT NO. 170