ML17318A381

Tech Specs 3.9.7-5.7 Re Spent Fuel Storage Pool Design, Capacity,Operation & Surveillance,For Unit 2

ML17318A381
Person / Time
Site:	Cook
Issue date:	10/16/1979
From:	INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17318A378	List: ML17318A377 ML17318A379 ML17318A380 ML17318A381 ML17318A382 ML17318A383 ML17318A385
References
NUDOCS 7911020265
Download: ML17318A381 (5)

Text

ATTACHMENT TO LICENSE AMENDMENT NO. 13 FACILITY OPERATING LICENSE NO.

DPR-74 DOCKET NO. 50-316 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.

The revised pages are identified by Amendment number of contain vertical lines indicating the area of change.

The corresponding overleaf pages are also provided to maintain document completeness.

~Pe es 3/4 9-7 5-5 5-6 D. C.

COOK - UNIT 2

REFUELING OPERATIONS CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING*

LIMITING CONDITION FOR. OPERATION 3.9.7 Loads in excess of 2,500 pounds shall be prohibited from travel over fuel assemblies in the storage pool.

Loads carried over the spent fuel pool and the heights at which they may be carried over racks containing fuel shall be limited in such a way as to preclude impact energies over 24,240 in.-lbs., if the loads are dropped from the crane.

APPLICABILITY: With fuel assemblies, in the storage pool.

ACTION:

With the requirements of the above specification not satisfied, place the crane load in a safe condition.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIRENENTS 4.9.7.1 Crane interlocks and physical stops which prevent crane travel with loads in excess of 2,500 pounds over fuel assemblies shall be demonstrated OPERABLE within 7 days prior to crane use and at least once per 7 days thereafter during crane operation.

4.9.7.2 The potential impact energy due to dropping the crane's load shall be determined to be ( 24,240 in.-lbs. prior to moving each load over racks containing fuel.

"Shared system with D.

C.

COOK - UNIT 1

D.

C.

COOK - UNIT 2 3/4 9-7 Amendment No. 13

REFUELING OPERATIONS COOLANT CIRCULATION LIMITING CONDITION FOR OPERATION 3.9.8 At least one residual heat removal loop shall be in operation..

APPLICABILITY: 'ODE 6.

ACTION:

'a ~

b.

c ~

With less than one residual heat removal loop in operation, except as provided in b. below, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System.

Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />'he residual heat removal loop may be removed from operation for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.8 A residual heat removal loop shall be determined to be in operation and circulating reactor coolant at a flow rate of

> 3000 gpm at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />'.

C.

COOK - UNIT2'/4 9-8

DESIGN FEATURES VQQQQE 5.4.2 The total water and steam volume of the reactor coolant system is 12,612

+ 100 cubic feet at a nominal T

of 70'F.

avg 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.

5.6 FUEL STORAGE CRITICALITV -

SPENT FUEL 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:

a.

A k ff equivalent to less than 0.95 when flooded with unborated eff water, which includes a conservative allowance of 2.6'i, delta k/k for uncertainties as described in Section 9.7 of the FSAR.

b.

A nominal 10.5 inch center-to-center distance between fuel assemblies, placed in the storate racks.

".6. 1.2 Fuel stored in the spent fuel storage racks shall have a maximum issi le fuel density of less than or equal to 44.2 grams of Uranium-235 er axial centimeter of fuel assembly or the reactivity equivalent thereof.

CRITICALITY -

NEW FUEL 5.6.2 The new fuel pit storage racks are designed and shall be maintained with a nominal 21 inch center-to-center distance between new fuel assem-blies such that k f. will not exceed 0.98 when fuel having a maximum enrichment of 3.5 whight percent U-235 is in place and aqueous foam oderation is assumed.

D.

C.

COOK - UNIT 2 5-5 Amendment No.

13

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