ML032801657

Technical Specifications, Changes to Technical Specifications Associated with Containment Building Penetrations

ML032801657
Person / Time
Site:	Seabrook
Issue date:	10/03/2003
From:	Nerses V NRC/NRR/DLPM/LPD1
To:
Shared Package
ML032801662	List: ML032801657
References
TAC MB6611
Download: ML032801657 (4)

Text

J. Additional Conditions The Additional Conditions contained in Appendix C, as revised through Amendment No. 94, are hereby incorporated into this license. FPL Energy Seabrook, LLC, shall operate the facility in accordance with the Additional Conditions.

3. This License is effective as of the date of issuance and shall expire at midnight on October 17, 2026.

FOR THE NUCLEAR REGULATORY COMMISSION (Original signed by:

Thomas E. Murley)

Thomas E. Murley, Director Office of Nuclear Reactor Regulation Attachments/Appendices:

1. Appendix A - Technical Specifications (NUREG-1386)

2. Appendix B - Environmental Protection Plan

3. Appendix C - Additional Conditions Date of Issuance: March 15, 1990 AMENDMENT NO. 6 94

REFUELING OPERATIONS I a314.9.4 CONTAINMENT BUILDING PENETRATIONS LIMING CONDITION FOR OPERATION I 3.9A The containment building penetrations shall be Inthe following status:

a. The equipment door dosed and held In place by a minimum of four bolts,

b. A minimum of one door Ineach aldock Is closed, however both doors of one personnel airlock may be open If:

1) One personnel airlock door Is capable of being dosed, and

2) A designated Individual Is available outside the personnel airlock to close the door.

c. Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be effler:

1) Closed by a manual or automatic solation valve, blind flange, or equivalent; or

2) Be capable of being closed by an OPERABLE automatic Containment Purge and Exhaust Isolation System; or

3) Be capable of being dosed by a designated Individual avalable at the penetration.*

APPLICABILITY: During movement of recently Irradiated fuel within the containment I ACTION:

With the requirements of the above specification not satisfied, Immediately suspend all operations Involving movement of recently Irradiated fuel Inthe containment building. I t A designated Individual shall not be used for manual Isolation of valves CAP-V1, CAP-V2, CAP-V3, andlor CAP-V4.

SEABROOK - UNIT 3f4 9-4 Amendment No. 4Q,& l

314.9 REFUELING OPERA7iONS BASES 314.9.2 INSTRUMENTA1ION The OPERABILITY of the Source Range Neutron Flux Monitors ensures that redundant monitoring capability Is available to detect changes Inthe reactivity condition of the core.

314.9.3 DECAY TIME The minimum requirement for reactor subcorilcaity prior to movement of Irradiated fuel assemblies Inthe reactor 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 Inthe safety analyses.

314.9A CONTAINMENT BUILDING PENETRAMONS The Lmiing Condition for Operation (LCO) limits the consequences of a fuel handring accident In containment by limiting the potential escape paths for fission product radioactivity released within containment The LCO requires any penetaton providing direct access from the containment atmosphere to the outside atmosphere to be losed xcept r the OPERABLE containment purge and exhaust penetrations, the approved alternate cosure methods and the containment personnel aldock For the approved alternate closure methods, the LCO requires that a designated Indivdual must be available to dose or direct the remote closure of the penetration Inthe event of a fuel handling accident Avlable' means stationed at the penetration or performing activities controlled by a procedure on equipment associated with the penetration. The Inside containment fuel handling accident analysis podes assurance that manual Isolation of penetration vles up to a 12Inch diameter size, thn the assumed time, can be attalned with the use of a degnat Wdhldual. With respect to the 36-Inch diameter CAP valves, a designated Indidual Is not allowed since manual closure would most likely exceed the assumed cdosurelIme.

Forthe personnel alocks (containment orequipent hatch), the LCO ensures that the aldock can be closed fter containment evacuation Inte event of a fuel handling accident The requirement that the airlock door Is capable of being dosed requires that the door can be dosed and Is not blocked by objects that cannot be easily and quicidy removed. As an example, the use of removable protective covers for the door seals and sealing surfaces Is permitted. The requrement for a designated individual located outside of the airlock area available to dose the door following evacuation of the containment will minimize the release of radioactive material.

The fuel handling accident aalysis Inside containment assumes all of the available activity Isassumed to be released Instantaneously from the containment to the atmosphere.

The OPERABILITY of the Containment Purge and Exhaust Isolation System ensures that the contaInment vent and purge penetrations will be automatically Isolated upon detection of high radiation levels within the containment. Te OPERABILMlY of this system Is required to restiict the release of radioactive material from the containment atmosphere to the environment SEABROOK- UNIT I B 314 9-2a Amirqat Nb. 94

314.9 REFUELING OPERATIONS BASES

'As described Inthe fuel handling analysis, there will be no pressurization of containment. Therefore, the requirements to Isolate the containment from the outside atmosphere can be less stringent. The LCO requirements during movement of recently iradiated fuel assemblies within the containment are referred to as "containment closure rather than containment OPERABILTY. The term recently Irradiated' fuel assembies Is defined as fuel that has occupied part of a critical reactor core within the previous 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.

For the containment to be OPERABLE, CONTAINMENT INTEGRITY must be maintained.

Containment closure means that all potential release paths are dosed or capable of being closed. Closure restrictions must be sufficient to provide a barrier to restrict radioactive material released from a fuel element rupture during refueling operations.

During the movement of non-recently irradiated fuel assemblies within the containment, there are no specific requirements for containment building penetration closure and OPERABILITY to ensure that a release of fission product radioactivity within containment will be resicted from leaking to the environment. However, t Is necessary to maintain the ability to Isolate containment penetrations to meet the applicable action statement requirements of TS 3.9.8.1 and 3.9.8.2 In the event that no OPERABLE RHR loops are In operation. During the movement of non-recently Irradiated fuel assemblies, the containment outage door may. be Installed as an altemative to nstalling the containment equipment hatch with a minimum of four bolts provided:

1. the reactor vessel upper Intemals have been removed; and

2. the water level above the top of the reactor vessel flange Is greater than or equal to 23 feet The containment outage door will be designed to ensure a release of fission product radiabtivfty within containment will be restricted from leaking to the environment due to a fuel handling accident during refueling operations. When the containrment outage door Is Installed and being used for containment closure In lieu of the equipment hatch, the following additional admInistrative requirements must be met:

1. The containment outage door will be nstalled and capable of being dosed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2. Hoses and cables being run through the containment outage door will employ a means to allow safe, quick disconnection or severance.

3. A designated ndiridual Is available and Indirect communication with the control room with the responsibility for the expeditious closure (within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) of the containment outage door Inthe event of a fuel handling accident.'

SEABROOK - UNIT i B 314 9-2b hremVmt lb. 94