ML20056E540

Amend 155 to License DPR-40,changing TS to Increase Fuel Storage Capacity in Spent Fuel Pool to 1083 Fuel Assemblies

ML20056E540
Person / Time
Site:	Fort Calhoun
Issue date:	08/12/1993
From:	Rood H Office of Nuclear Reactor Regulation
To:
Shared Package
ML20056E539	List: ML20056E538 ML20056E540 ML20056E541
References
NUDOCS 9308240233
Download: ML20056E540 (10)

Text

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ePrag% UNITED STATES E k2 E NUCLEAR REGULATORY COMMISSION lj2Jgl[j[

yn wAssisotoN. o.c. 20sss.ooo1 OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 155 License No. DPR-40

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by the Omaha Public Power District (the licensee) dated December 7, 1992, as supplemented by letters dated March 19, April 28, and May 14, 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; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. 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 license amendment will not be inimical to the i 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, Facility Operating License No. DPR-40 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No.

DPR-40 is hereby amended to read as follows: -

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

9308240233 930812 PDR ADOCK 050002G5 P PDR

3. Accordingly, the license is hereby amended by a change to paragraph 3.D of Facility Operating License No. DPR-40 to read as follows:

3.D. Spent Fuel Pool Modification The licensee is authorized to modify the spent fuel pool as described in the application dated December 7, 1992, as supplemented by letters dated March 19, April 28, and May 14, 1993. The modification shall consist of removing the existing racks which have a storage capacity of 729 fuel assemblies and inserting new racks which will have a storage capacity of 1083 fuel assemblies. There shall be 11 free-standing rack modules in a discrete-zone, two-region storage system.

The Appendix A Technical Specifications shall be effective as follows:

o Changes to Specifications 2.8(11) and (12), 4.4.2, and 5.10.3 and Figure 2-10, Table 3-5, and the basis for Specification 2.8 shall be effective when the last new rack is installed.

4. The license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Harry Roo , Acting Director Project Directorate IV-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation Attachments:

1. Page 4a of license *

2. Changes to the Technical Specifications Date of Issuance: August 12, 1993

• Page 4a is attached for convenience so that the composite license reflects this change.

1

^

- 4a -

l i

i D. Spent Fuel Pool Modification '

The licensee is authorized to modify the spent fuel pool as described in the application dated December 7, 1992, as supplemented ,

by letters dated March 19, April 28, and May 14, 1993. The  ;

modification shall consist of removing the existing racks which have  !

a storage capacity of 729 fuel assemblies and inserting new racks ,

which will have a storage capacity of 1083 fuel assemblies. There shall be 11 free-standing rack modules in a discrete-zone, two- I region storage system.  ;

The Appendix A Technical Specifications shall be effective as follows:

o Changes to Specifications 2.8(11) and (12), 4.4.2, and 5.10.3 I and Figure 2-10, Table 3-5, and the basis for Specification 2.8 shall be effective when the last new rack is installed. <

4. This amended license is effective as of the date of issuance and shall  !

expire at midnight on June 7, 2008.  !

FOR THE NUCLEAR REGULATORY COMMISSION  !

Original signed by:

A. Giambusso l

A. Giambusso, Deputy Director for Reactor Projects  !

Directorate of Licensing  !

Enclosures.

Appendices A and B - Technical Specifications i i

Date of Issuance: August 9, 1973 t

i I

i 1

Amendment No.155 f

i t

ATTACHMENT TO LICENSE AMENDMENT NO.155 l

FACILITY OPERATING LICENSE N0. DPR-40 DOCKET NO. 50-285 l Revise Appendix "A" Technical Specifications as indicated below. The revised  !

pages are identified by amendment number and contain vertical lines indicating l the area of change.  :

FEMOVE PAGES INSERT PAGES i 2-38 2-38 Figure 2-10 Figure 2-10 i 2-39 2-39 .

3-20d 3-20d  !

4-4 4-4 i i

5-19 5-19 i

b I

9 d

2.0 LIMITING CONDITIONS FOR OPERATION ,

2.8 Refueling Onerations (Continued)

(6) Direct communication between personnel in the control room and at the refueling

~

machine shall be available whenever changes iu core geometry are taking place.

(7) When irradiated fuel is being handled in the auxihary building, the exhaust i ventilation from the spent fuel pool area will be diverted through the charcoal  ;

filter.  ;

i (8) Prior to initial core loading and prior to refueling operations, a complete check

. out, including a load test, shall be conducted on fuel handling cranes that will be ,

required during the refueling operation to handle spent fuel assemblies.

(9) A minimum of 23 feet of water above the top of the core shall be maintained  !

whenever irradiated fuel is being handled.

(10) Storage in Region 1 and Region 2 of the spent fuel racks shall be restricted to fuel assemblies having initial enrichment less or equal to 4.0 weight percent of U-235.  ;

(11) Storage in Region 2 of the spent fuel racks shall be restricted to those assemblies whose parameters fall within the " acceptable" area of Figure 2-10. Storage in the peripheral cells of Region 2 shall be restricted to those assemblies whose  ;

parameters fall within the noted area of Figure 2-10.

(12) A minimum boron concentration of 100 ppm shall be maintained in the Spent Fuel Pool whenever storing unitradiated fuel in the Spent Fuel Pool.

If any of the above conditions are not met, all refueling operations shall cease  !

immediately, work shall be initiated to satisfy the required conditions, and no operations that may change the reactivity of the core shall be made.

A spent fuel assembly may be transferred directly from the reactor core to the spent fuel  ;

pool Region 2 provided the independent verification of assembly burnups has been '

completed and the assembly burnup meets the acceptance criteria identified in Technical Specification Figure 2-10.

Movement of irradiated fuel from the reactor core shall not be initiated before the reactor l core has been subcritical for a minimum of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if the reactor has been operated at  !

power levels in excess of 2% rated power.

Bases The equipment and general procedures to be utilized during refueling operations are  !

discussed in the USAR. Detailed instructions, the above specifications, and the design  ;

of the fuel handling equipment incorporating built-in interlocks and safety features provide assurance that no incident could occur during the refueling operations that would 2-38 Amendment No. 5,24,25,43,75,133,152, 155 i

i FIGURE 2-10 1

37500 35000 : .

32500 :

30000 : /

27500 3 ACCEPTABLE /

3 BJRNUP DOMAIN / ,

r 25000 : / .

% *g/ s' '

i 22500 .5 ,'

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20000l 17500 _ y f 'j'f ,

s ua s

15000 : '$/ ' 8' e i $ /> ,y*

12500 - r

! / <

10000

[, ' ' > UNACCEPTnBLE 7500:!

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, BUFNUP D0iAIN 5000 _

, ( Re cuires Region 1 Storege) 2500 :

/',,

0: ./. .

1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 INITIAL ENRICHMENT, wt% U235 LIMITING BURNUP CRITERIA FOR ACCEPTABLE STORAGE IN REGION 2 NOTE: 1. Ang fuel essembly (24.2% U235 overege) mechanically coupled with a full length CEA meg be located engwhere in Region 2.

2. Peripheral cells are those adjacent to the Spent Fuel Pool well or the cesk legdown area.

Amendment No. M;433,155

2.0 LIMITING CONDITIONS FOR OPERATION 2.8 Refuelinn Ooerations (Continued) i result in a hazard to public health and safety.m Whenever changes are not being made in core geometry one flux monitor is sufficient. This permits maintenance of the instrumentation. Continuous monitoring of radiation levels and neutron flux provides immediate indication of an unsafe condition. The shutdown cooling pump is used to maintain a uniform boron concentration.

The shutdown margin as indicated will keep the core suberitical even if all CEA's were withdrawn from the core. During refueling operations, the reactor refueling casity is ,

filled with approximately 250,000 gallons of borated water. The boron concentration of this water (of at least the refueling boron concentration) is sufficient to maintain the ,

reactor suberitical by more than 5 %, including allowance for uncertainties, in the cold condition with all rods withdrawn.m Periodic checks of refueling water boron concent'ation ensures the proper shutdown margin. Communication requirements allow the conwol room operator to inform the refueling machine operator of any impending unsafe condition detected from the main control room board indicators during fuel movement.

In addition to the above engineered safety features, interlocks are utilized during refueling operations to ensure safe handling. An excess weight interlock is provided on the lifting hoist to prevent movement of more than one fuel assembly at a time. In addition, interlocks on the auxiliary building crane will prevent the trolley from being moved over storage racks containing irradiated fuel, except as necessary for the handling of fuel. The restriction of not moving fuel in the reactor for a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after the power has been removed from the core takes advantage of the decay of the short half-life fission products and allows for any failed fuel to purge itself of fission gases, thus 2 reducing the consequences of fuel handling accident.

The ventilation air for both the containment and the spent fuel pool area flows through absolute particulate filters and radiation monitors before discharge at the ventilation discharge duct. In the event the stack discharge should indicate a release in excess of the limits in the technical specifications, the containment ventilation flow paths will be closed automatically and the auxiliary building ventilation flow paths will be closed manually. In addition, the exhaust ventilation ductwork from the spent fuel storage area is equipped with a charcoal filter which will be manually put into operation whenever irradiated fuel is being handled.m The basis for the 100 ppm boron concentration requirement with Boral poisoned storage racks is to maintain the km below 0.95 in the event a misplaced unirradiated fuel assembly is located next to a spent fuel assembly. A misplaced unirradiated fuel assembly at 4.2 w/o enrichment condition, in the absence of soluble poison, may result in exceeding the design effective multiplication factor. Soluble boron in the Spent Fuel Pool water, for which credit is permitted under these conditions, would assure that the effective multiplication factor is maintained substantially less than the design condition.

The boron concentration is periodically sampled in accordance with Specification 3.2.

References (1) USAR, Section 9.5 (2) USAR, Section 9.5.1.2 2-39 Amendment No. 24,75,103,117,133,141,155

TABLE 3-5 (Continued) '

USAR Section Test Fanuu,0 -

Reference 10c. (continued) 4. Automatic and/or manual initi- At least once per plant operating cycle.

ation of the system shall be demonstrated. j

11. Containment Cool- 1. Demonstrate damper action. I year, 2 years, 5 years, and every 5 9.10 ing and lodine years thereafter.

Removal Fusible Linked Dampers 2. Test a spare fusible link.

12. Diesel Generator Calibrate During each refueling outage. 8.4.3 Under-Voltage Relays

13. Motor Opted Verify the contactor pickup value at During each refueling outage.

Safety injection 5,85% of 460 V.

Loop \ alve Motor Starters ()(CV-311, 314,317,320,327, 329,331,333,312, 315, 318, 321) j 14. Pressurizer llesters Verify control circuits operation During each refueling outage.

j for post-accident heater use.

15. Spent Fuel Pool Test neutron poison samples for I, 2, 4, 7, and to years after j Region i Racks dimensional change, hardness change, installation, and every 5 years weight, neutron attenuation change thereafter.

and specific gravity change.

16. Reactor Coolant 1. Verify all manual isolation During each refueling outagejust Gas Vent System valves in each vent path are prior to plant start-up.

• I in the open position.

2. Cycle each automatic valve in During each refueling outage.

the vent path through at least one complete cycle of full travel from the control room.

Verification of valve cycling may be determined by olmtva-tion of position indicating lights.

3. Verify flow through the reactor During each refueling outage, coolant vent system vent paths.

3-20d Ammdment No. ,51.".'5,7?,=,155

4.0 DESIGN FEATURES 4.4 Fuel Storace 4.4.1 New Fuel Storace The new unirradiated fuel bundles will normally be stored in the dry new fuel storage rack with an effective multiplication factor of less than 0.9. The open grating floor below the rack and the covers above the racks, along with generous provision for drainage, precludes flooding of the new fuel storage rack.

New fuel may also be stored in shipping containers or in the spent fuel pool racks which have a maximum effective multiplication factor of 0.95 with Fort Calhoun Type C fuel and unborated water.

The new fuel storage racks are designed as a Class I structure.

4.4.2 Stent Fuel Storace Irradiated fuel bundles will be stored prior to off-site shipment in the stainless steel lined spent fuel pool. The spent fuel pool is normally filled with borated water with a concentration of at least the refueling boron concentration.

The spent fuel racks are designed as a Class I structure.

Normally the spent fuel pool cooling system will maintain the bulk water temperature of the pool below 120'F. Under other conditions of fuel discharge, the fuel pool water temperature is maintained below 14CTF.

The spent fuel racks are designed and will be maintained such that the calculated effective multiplication factor is no greater than 0.95 (including all known -

uncertainties) assuming the pool is flooded with unborated water. The racks are divided into 2 regions. Region 1 and 2 cells are surrounded by Boral. Acceptance l criteria for fuel storage in Regions 1 and 2 are delineated in Section 2.8 of these Technical Specifications.

4-4 Amendrr.ent No. 13,43,75,103, 133,141,155

5.0 ADMINISTRATIVE CONTROLS 5.10.2 The following records shall be retained for the duration of the Facility Operating License:

a. Records of drawing changes reflecting facility design modifications made to systems and equipment described in the Final Safety Analysis Report.

b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

c. Records of facility radiation and contamination surveys,

d. Records of radiation exposure for all individuals entering radiation control areas.

c. Records of gaseous and liquid radioactive material released to the environs.

f. Records of transient or operational cycles for those facility components designed for a limited number of transients or cycles.

g. Records of training and qualification for current members of the plant staff.

h. Records of in-service inspections performed pursuant to these Technical Specifications.

i. Records of Quality Assurance activities required by the QA Manual.

j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

k. Records of meetings of the Plant Review Committee and the Safety Audit and Review Committee.

1. Records of Environmental Qualification of Electric Equipment pursuant to 10 CFR 50.49.

m. Records of the se>vice lives of all hydraulic and mechanical snubbers which are covered mder the provisions of Section 2.18 of the Technical Specifications, inch ding the date at which the service life commences and associated installa6on and maintenance records.

n. Records of analyses required by the Radiological Environmental Monitoring Program.

o. Records of reviews performed for changes made to the Offsite Dose Calculation Manual and the Process Control Program.

5.10.3 A complete record of the analysis employed in the selection of any fuel assembly to be placed in Region 2 of the spent fuel racks will be retained as long as that assembly remains in Region 2 (reference Technical Specifications 2.8 and 4.4).

l 5.11 Radiation Protection Procram Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

5-19 Order 70/2"S0 Amendment No. 59,86,93,99,105,152,155