ML17328A717

Proposed Tech Specs Re Limiting Conditions for Operation & Surveillance Requirements for Steam Generator Stop Valves & ESF Response Times

ML17328A717
Person / Time
Site:	Cook
Issue date:	05/14/1990
From:	INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17328A716	List: ML17328A715 ML17328A717 ML17328A728
References
NUDOCS 9005220066
Download: ML17328A717 (8)

Text

ATTACHMENT 2 TO AEP:NRC:1123 PROPOSED REVISED TECHNICAL SPECIFICATION PAGES

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PLANT SYSTEMS STEAM GENERATOR STOP VALVES LIMITING CONDITION FOR OPERATION 3.7.1.5 Each steam generator stop valve shall be OPERABLE'PPLICABILITY:

MODES 1, 2 and 3.

ACTION:

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 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; otherwise, reduce power to less than or equal to 5 percent of RATED THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

MODES 2 - With one steam generator stop valve inoperable, subsequent and 3 operation in MODES 2 or 3 may proceed provided:

a. The stop valve is maintained closed.

b. The provisions of Specification 3.0.4 are not applicable.

Otherwise, 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 4.7.1.5.1 Each steam generator stop valve 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 2 3/4 7-10 AMENDMENT NO ~

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TABLE 3.3-5 Continued ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS

3. Pressurizer Pressure-Low

a. Safety Injection (ECCS) Less than or equal to 24.0*/12.0¹

b. Reactor Trip (from SI) Less than or equal to 2.0 C. Feedwater Isolation Less than or equal to 8.0

d. Containment Isolation-Phase "A" Less than or equal to 18.0¹

e. Containment Purge and Exhaust Isolation Not Applicable Motor Driven Auxiliary Feedwater Pumps E Less than or equal to 60.0 Essential Service Water System Less than or equal to 48.0*/13.0¹

4. Differential Pressure Between Steam Lines-Hi h

a. Safety Injection (ECCS) Less than or equal to 12.0¹/24.0¹¹

.b. Reactor Trip (from SI) Less than or equal to 2.0 C. Feedwater Isolation Less than or equal to 8.0

d. Containment Isolation-Phase "A" Less than or equal to 18.0¹/28.0¹¹

e. Containment Purge and Exhaust Isolation Not Applicable Motor Driven Auxiliary Feedwater Pumps Less than or equal to 60..0 Essential Service Water System Less than or equal to 13.0¹/48.0¹¹

5. Steam Flow in Two Steam Lines - Hi h Coincident with Tav --Low-Low

a. Safety Injection (ECCS) Not Applicable

b. Reactor Trip (from SI) Not Applicable C. Feedwater Isolation Not Applicable

d. Containment Isolation-Phase "A" Not Applicable

e. Containment Purge and Exhaust Isolation Not Applicable Auxiliary Feedwater Pumps Not Applicable

g. Essential Service Water System Not Applicable

h. Steam Line Isolation Less than or equal to 13.0 COOK NUCLEAR PLANT - UNIT 2 3/4 3-27 AMENDMENT NO ~

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TABLE 3.3-5 Continued ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS

6. Steam Line Pressure--Low

a. Safety Injection (ECCS) Less than or equal to 12.0¹/24.0¹¹

b. Reactor Trip (from SI) Less than or equal to 2.0 C. Feedwater Isolation Less than or equal to 8.0

d. Containment Isolation-Phase "A" Less than or equal to 18.0¹/28.0¹¹

e. Containment Purge and Exhaust Isolation Not Applicable Motor Driven Auxiliary Feedwater Pumps Less than or equal to 60.0 g Essential Service Water System Less than or equal to 14.0¹/48.0¹¹

h. Steam Line Isolation Less than or equal to 11.0

7. Containment Pressure--Hi h-Hi h

a. Containment Spray Less than or equal to 45.0

b. Containment Isolation-Phase "B" Not Applicable C. Steam Line Isolation Less than or equal to 10.0

d. Containment Air Recirculation Fan Less than or equal to 600.0

8. Steam Generator Water Level--Hi h-Hi h

a. Turbine Trip Not Applicable

b. Feedwater Isolation Not Applicable

9. Steam Generator Water Level--Low-Low Motor Driven Auxiliary Feedwater Pumps

• Less than or equal to 60.0 Turbine Driven Auxiliary Feedwater Pumps Less than or equal to 60.0

10. 4160 volt Emer enc Bus Loss of Volta e

a. Motor Driven Auxiliary Feedwater Pumps Less than or equal to 60.0

11. Loss of Main Feedwater Pum s

a. Motor Driven Auxiliary Feedwater Pumps Less than or equal to 60.0

12. Reactor Coolant Pum Bus Undervolta e

a. Turbine Driven Auxiliary Feedwater Pumps Less than or equal to 60.0 COOK NUCLEAR PLANT - UNIT 2 3/4 3-28 AMENDMENT NO.

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ATTACHMENT 3 TO AEP:NRC:1123 ANALYSIS OF MAIN STEAM LINE BREAK INSIDE CONTAINMENT (WCAP-11902 SUPPLEMENT 1)