ML072220040

Issuance of Amendments Miscellaneous Technical Specifications

ML072220040
Person / Time
Site:	Prairie Island
Issue date:	08/10/2007
From:	Mahesh Chawla NRC/NRR/ADRO/DORL/LPLIII-1
To:	Wadley M Nuclear Management Co
Chawla M, NRR/DORL/LPL3-1, 301-415-8371
Shared Package
ML071660002	List: ML071660005 ML072220040
References
TAC MD2822, TAC MD2823
Download: ML072220040 (6)

Text

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-4 (continued)

If the Completion Time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (plus the extension) expires while one or more valves are still inoperable, Condition B is entered.

EXAMPLE 1.3-5 ACTIONS NOTE Separate Condition entry is allowed for each inoperable valve.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A. 1 Restore valve to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> valves OPERABLE inoperable, status.

B. Required B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action and associated AND Completion Time not B.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> met.

The Note above the ACTIONS Table is a method of modifying how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was applicable only to a specific Condition, the Note would appear in that Condition rather than at the top of the ACTIONS Table.

Prairie Island Unit 1 - Amendment No. 4-58 180 Units ! and 2  !.3-1! Unit 2 - Amendment No. IA-9 170

Rod Group Alignment Limits 3.1.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify individual rod positions within alignment 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> limit.

SR 3.1.4.2 Verify rod freedom of movement (trippability) by 92 days moving each rod, not fully inserted in the core,

> 10 steps in either direction.

SR 3.1.4.3 Verify rod drop time of each rod, from the fully Prior to reactor withdrawn position, is < 1.8 seconds from the criticality after beginning of decay of stationary gripper coil voltage each removal of to dashpot entry, with: the reactor head

a. Tavg> 500'F; and

b. Both reactor coolant pumps operating.

Prairie Island Unit 1 - Amendment No. 4-54 180

~21A A -I,,:.I 2 ANo. r-ý* ~ ,r 1-4% 170 Units I and 2 I.)IL -- Cg- lkl *Sh nALI.tl L q.

SFPSVS Actuation Instrumentation 3.3.7 Table 3.3.7-1 (page I of i)

SFPSVS Actuation Instrumentation APPLICABLE MODES OR SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS REQUIREMENTS VALUE I. Fuel Pool (a) I per train SR 3.3.7.1 (b)

Enclosure SR 3.3.7.2 Radiation SR 3.3.7.3 (a) During movement of irradiated fuel assemblies in the fuel pool encbsure.

(b) This value provided by the ODCM.

Prairie Island Unit 1 - Amendment No. 4-58 180 Units i and 2 I) I '7_A Unit 2 - A. endment No. 4.49 170

CRSVS 3.7.10 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A or B AND not met in MODE 1, 2, 3, or 4. C.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> D. Required Action and D.I Place OPERABLE CRSVS Immediately associated Completion train in operation.

Time of Condition A not met during movement of OR irradiated fuel assemblies.

D.2 Suspend movement of Immediately irradiated fuel assemblies.

E. Two CRSVS trains E. I Suspend movement of Immediately inoperable during irradiated fuel assemblies.

movement of irradiated fuel assemblies.

F. Two CRSVS trains F.1 Enter LCO 3.0.3. Immediately inoperable in MODE 1, 2, 3, or 4 for reasons other than Condition B.

Prairie Island Unit I - Amendment No. 41-58 180 Units1I, an1 2- 3.7.10-2 Unit 2 - Amendmnent No. -49 170

CRSVS 3.7.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Operate each CRSVS train > 15 minutes. 31 days SR 3.7.10.2 Perform required CRSVS filter testing in In accordance accordance with the Ventilation Filter Testing with VFTP Program (VFTP).

SR 3.7.10.3 Verify. each CRSVS train actuates on an actual or 24 months simulated actuation signal.

SR 3.7.10.4 Verify each CRSVS train in the Emergency Mode 24 months on a delivers 3600 to 4400 cfm through the associated STAGGERED CRSVS filters. TEST BASIS Prairie Island Unit 1 - Amendment No. 4-5-8 180 L-t 1 l,I I d lU , 3 .7.10-3 Unit 2 - Aiend.m.entN. ir-4 0

Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage (continued) 4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage

-capacity limited to no more than 1386 fuel assemblies not including those assemblies which can be returned to the reactor. The southeast corner of the small pool serves as the spent fuel cask lay down area. To facilitate plant evolutions, four additional storage racks, with a combined capacity of 196, may be temporarily installed in the cask lay down area to provide a total of 1582 storage locations (Ref. 3).

REFERENCES 1. "Prairie Island Units 1 and 2 Spent Fuel Pool Criticality Analysis", WCAP-16517-NP, Revision 0, Westinghouse Electric Company, November 2005.

2. "Criticality Analysis of the Prairie Island Units 1 & 2 Fresh and Spent Fuel Racks", Westinghouse Commercial Nuclear Fuel Division, February 1993.

3. USAR, Section 10.2.

Prairie Island Unit 1 - Amendment No. 15&8 172 180 Units I an- 2 .4 r--A

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