ML20092N289

Amend 166 to License NPF-6,revising Specifications to Permit Containment Personnel Airlock Doors to Remain Open During Fuel Handling

ML20092N289
Person / Time
Site:	Arkansas Nuclear
Issue date:	09/28/1995
From:	Kalman G Office of Nuclear Reactor Regulation
To:
Shared Package
ML20092N290	List: ML20092N289 ML20092N292
References
NPF-06-A-166 NUDOCS 9510050240
Download: ML20092N289 (7)

Text

-.

pn usuq%

u-o.mo s

j NUCLEAR REGULATORY COMMISSION 4

2 WASHINGTON D.C. - %

4.....$

ENTERGY OPERATIONS. INC.

DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE. UNIT NO. 2 i

AMENDMENT TO FACILITY OPERATING LICENSE i

Amendment No.166 License No. NPF-6

~

1.

The Nuclear Regulatory Commission (the Comission) has found that:

A.

The application for amendment by Entergy Operations, Inc. (the licensee) dated May 19, 1995, as supplemented July 21, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; l

B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 4

j.

C.

There is reasonable assurance:

(i) that the activities authorized by this amendment can be conducted without endangering the health i

and safety of the public, and (ii) that such activities will be

{

conducted in compliance with the Comission's regulations; D.

The issuance of this license amendment will not be inimical to the l

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 I

of the Comission's regulations and all applicable requirements have been satisfied.

I

\\

4 g0050240950928 l

p ADOCK 05000368 PDR

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. NPF-6 is hereby amended to read as follows:

2.

Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.166, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

The license amendment is effective as of the date of issuance, to be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION

^

-C./)

George Kalman, Senior Project Manager Project Directorate IV-1 i

Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: September 28, 1995 os 1

4 i

\\

ATTACHMENT TO LICENSE AMENDMENT NO.166 FACILITY OPERATING LICENSE NO. NPF-6 j

DOCKET NO. 50-368 Revise the following pages of the Appendix "A" Technical Specifications with the attached pages.

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

overleaf pages are also provided to maintain document completeness.

2 REMOVE PAGES INSERT PAGES 3/4 9-3 3/4 9-3 3/4 9-4 3/4 9-4 B 3/4 9-1 B 3/4 9-1 B 3/4 9-3 B 3/4 9-3 so i

e

REFUELING OPERATIONS DECAY TIME AND SPENT FUEL STORAGE LIMITING CONDITION POR OPERATION 3.9.3.a The reactor shall be suberitical for at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />.

l 3.9.3.b In the event of a complete core offload, a full core to be discharged shall be subcritical a minimum of 175 hours0.00203 days <br />0.0486 hours <br />2.893519e-4 weeks <br />6.65875e-5 months <br /> prior to discharge of more than 70 assemblies to the spent fuel pool.

APPLICASILITYt During movement of irradiated fuel in the reactor pressure vessel.

ACTION With the reactor suberitical for less than 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, suspend all operations l

involving movement of irradiated fuel in the reactor pressure vessel. With the reactor suberitical for less than 175 hours0.00203 days <br />0.0486 hours <br />2.893519e-4 weeks <br />6.65875e-5 months <br />, suspend all operations involving movement of more than 70 fuel assemblies from the reactor j

pressure vessel to the opent fuel pool. The provisions of specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.3.a The reactor shall be determined to have been suberitical for at least 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> by verification of the date and time of suberiticality prior l

to movement of irradiated fuel in the reactor pressure vessel.

4.9.3.b The reactor shall be determined to have been suberitical for at least 175 hours0.00203 days <br />0.0486 hours <br />2.893519e-4 weeks <br />6.65875e-5 months <br /> by verification of the date and time of subcriticality prior to movement of the 71st irradiated fuel assembly from the reactor pressure vessel to the spent fuel pool.

as l

l l

1 4

4 i

i I

ARKANSAS - UNIT 2 3/4 9-3 Amendment No. 44

1

' REFUELING OPERATIONS CONTAINMENT BUILDING PENETRATIONS LIMITING CONDITION FOR OPERATION 3.9.4 The containment building. penetrations shall be in the following status:

a.

The equipment door closed and held in place by a minimum of four

bolts, b.

A minimum of one door in each airlock is capable.of being closed, and l

c.

Each penetration providing direct access from the containment j

atmosphere to the outside atmosphere shall be either:

1.

Closed by an isolation valve, blind flange, or manual valve, or 2.

Exhausting through OPERABLE containment purge and exhaust system HEPA filters and charcoal adsorbers.

APPLICABILITY:

During CORE ALTERATIONS or movement of irradiated fuel

-within the containment.

ACTION:

With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.4.1 Each of the above required containment penetrations shall be determined to be in its above required condition within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONS or movement of irradiated fuel in the containment.

j 4.9.4.2.

The containment purge and exhaust system shall be demonstrated OPERABLE at the following frequencies:

At least once per 18 months or (1)af ter any structural a.

maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system by:

l ARKANSAS - UNIT 2 3/4 9-4 Amendment No.166

3/4.9 RETUELING OPERAT2ONS BASES 3/4.9.1 BORON CONCENTRATION The limitations on reactivity conditions during REFUELING ensure that: 1) the reactor will remain suberitical during CORE ALTERATIONS, and

2) a uniform boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel.

These limitations are consistent with the initial conditions assumed for the boron dilution incident in the accident analyses.

3/4.9.2 INSTRUMENTATION The OPERABILITY of the source range neutron flux monitors ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core.

3/4.9.3 DECAY TIME The minimum requirement for reactor suberiticality prior to movement of irradiated fuel assemblies in the reactor pressure vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short-lived fission products. This decay time is consistent with the assumptions used in the accident analyses.

The minimum requirement for reactor suberiticality prior to movement of more than 70 irradiated fuel assemblies to the spent fuel pool ensures that sufficient time has elapsed to allow radioactive decay of the short lived fission products such that the heat generated will not exceed the cooling capacity of the spent fuel pool cooling system.

This decay time and total assembly limitation is conservatively within the assumptions used in the accident analyses.

3/4.9.4 CONTAINMENT PENETRATIONS The requirements on containment penetration closure and OPERABILITY of the containment purge and exhaust system HEPA filters and charcoal adsorbers ensure that a release of radioactive material within containment will be restricted from leakage to the environment or filtered through the HEPA filters and charcoal adsorbers prior to discharge to the atmosphere.

The OPERABILITY and closure restrictions are,eufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization potential while in the RETUELING MODE.

Operation of the containment purge and exhaust system HEPA filters and charcoal adsorbers and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses.

The containment personnel airlock doors may be open during movement of irradiated fuel in the containment and during CORE ALTERATIONS provided a minimum of one door is capable of being closed in the event of a fuel handling accident and the plant is in MODE 6 with 23 feet of water above the fuel seated within the reactor pressure vessel.

Should a fuel handling accident occur inside containment, a minimum of one personnel airlock door will be closed following an evacuation of containment.

ARKANSAS - UNIT 2 B 3/d 9-1 Amendment No. JA

d i

)

REFUELING OPERATIQMS BASES t

l 3/4.9.9 and 3/4.9.10 WATER LEVEL-REACTOR VISSEL AND SPENT FUEL POOL l

WATER LEVEL The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 124 iodine gap activity l

released from the rupture of an irradiated fuel assembly. The minimum water depth is consistent with the assumptions of the accident analysis.

I 3/4.9.11 FUEL HANDLING AREA VENTILATION SYSTEM i

j The limitations on the fuel handling area ventilation system ensure that all radioactive materials released from an irradiated fuel assembly will be filtered through the MIPA filters and charcoal adsorbers prior to discharge to the atmosphere. The operation of this system and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses.

3/4.9.12 FUEL STORACE i

Region 1 of the spent fuel storage racks is designed to assure fuel assemblies of less than or equal to 4.1 w/o U-235 enrichment will be f

maintained in a suberitical array with K,gg 50.95 in unborated water.

These conditions have been verified by criticality analyses.

j

~

Region 2 of the spent fuel storage racks is designed to assure fuel f

assemblies within the burnup and initial enrichment limits of Figure 3.9.2

{

will be maintained in a subcritical array with K,gg 50.95 in unborated j

water. These conditions have been verified by criticality analyses.

The requirement for 1600 ppe boron concentration is to assure the fuel i

assemblies will be maintained in a suberitical array with K,gg'50.95 in the event of a postulated accident.

as i

I 1

4 f

4 J

l AREANSAS - UNIT 2 5 3/4 9-3 Amendment No. 44 f

-