ML042860246
| ML042860246 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 09/30/2004 |
| From: | NRC/NRR/DLPM/LPD2 |
| To: | |
| References | |
| TAC MC0625, TAC MC0626 | |
| Download: ML042860246 (7) | |
Text
Containment Penetrations 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Containment Penetrations LCO 3.9.3 The containment penetrations shall be In the following status:
- a. The equipment hatch is capable of being closed and held in place by four bolts; I
- b. One door In each air lock closed; and
- c. Each penetration providing direct access from the containment atmosphere to the outside atmosphere either:
- 1. closed by a manual or automatic isolation valve, blind flange, or equivalent, or
- 2. capable of being closed by an OPERABLE Containment Purge and Exhaust Isolation System.
APPLICABILITY: During CORE ALTERATIONS, During movement of Irradiated fuel assemblies within containment.
ACTIONS .=_ ,._
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more containment A.1 Suspend CORE Immediately penetrations not in ALTERATIONS.
required status.
AND A.2 Suspend movement of Immediately Irradiated fuel assemblies within containment.
Farley Units 1 and 2 3.9.3-1 Amendment No. 165 (Unit 1)
Amendment No. 157 (Unit 2)
Containment Penetrations 3.9.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Verify each required containment penetration is In the 7 days required status.
SR 3.9.3.2 Verify each required containment purge and exhaust 18 months valve actuates to the isolation position on an actual or simulated actuation signal.
SR 3.9.3.3 NOTE-- 7 days Only required for an open equipment hatch.
Verify the capability to install the equipment hatch.
Farley Units 1 and 2 3.9.3-2 Amendment No. 1 65 (Unit 1)
Amendment No. 1 5 7 (Unit 2)
Containment Penetrations B 3.9.3 B 3.9 REFUELING OPERATIONS B 3.9.3 Containment Penetrations BASES BACKGROUND During CORE ALTERATIONS or movement of irradiated fuel assemblies within containment, a release of fission product radioactivity within containment will be restricted from escaping to the environment when the LCO requirements are met. In MODES 1, 2,3, and 4, this is accomplished by maintaining containment OPERABLE as described In LCO 3.6.1, "Containment." In MODE 6, the potential for containment pressurization as a result of an accident is not likely; therefore, requirements to isolate the containment from the outside atmosphere can be less stringent. The LCO requirements are referred to as wrefueling integrity" rather than containment OPERABILITY.' Refueling integrity means that all potential escape paths are closed or capable of being closed. Since there Is no potential for containment pressurization, the 10 CFR 50, Appendix J leakage criteria and tests are not required.
The containment serves to contain fission product radioactivity that may be released from the reactor core following an accident, such that offsite radiation exposures are maintained well within the requirements of 10 CFR 100. Additionally, the containment provides radiation shielding from the fission products that may be present in the containment atmosphere following accident conditions.
The containment equipment hatch, which is part of the containment pressure boundary, provides a means for moving large equipment and components Into and out of containment. If closed, the equipment hatch must be held in place by at least four bolts. Good engineering practice dictates that the bolts required by this LCO be approximately -equallyspaced. Alternatively, the equipment hatch can be open provided it can be Installed with a minimum of four bolts holding it In place.
The containment air locks, which are also part of the containment pressure boundary, provide a means for personnel access during MODES 1, 2,3, and 4 unit operation In accordance with LCO 3.6.2, Containment Air Locks.' Each air lock has a door at both ends. The doors are normally interlocked to prevent simultaneous opening when containment OPERABILITY is required. During periods of unit shutdown (continued)
Farley Units 1 and 2 B 3.9.3-1 Revision
Containment Penetrations B 3.9.3 BASES BACKGROUND isolation valve, a manual Isolation valve, blind flange, or equivalent.
(continued) Equivalent Isolation methods allowed under the provisions of 10 CFR 50.59 may include use of a material that can provide a temporary, atmospheric pressure, ventilation barrier for the other containment penetrations during CORE ALTERATIONS or movement of irradiated fuel assemblies within containment (Ref. 1).
APPLICABLE During CORE ALTERATIONS or movement of Irradiated fuel SAFETY ANALYSES assemblies within containment, the most severe radiological consequences result from a fuel handling accident. The fuel handling accident is a postulated event that Involves damage to Irradiated fuel (Ref. 2). The fuel handling accident analyzed includes dropping a single irradiated fuel assembly. The requirements of LCO 3.9.6, "Refueling Cavity Water Level," and the minimum decay time of 100 hours4.167 days <br />0.595 weeks <br />0.137 months <br /> prior to CORE ALTERATIONS ensure that the release of fission product radioactivity, subsequent to a fuel handling accident, results In doses that are well within the guideline values specified In 10 CFR 100. Standard Review Plan, Section 15.7.4, Rev. 1 (Ref. 3),
defines "well within' 10 CFR 100 to be 25% or less of the 10 CFR 100 values. The acceptance limits for offsite radiation exposure will be 25% of 10 CFR 100 values.
Containment penetrations satisfy Criterion 3 of 10 CFR 50.36(c)(2)(ii).
LCO This LCO limits the consequences of a fuel handling accident in containment by limiting the potential escape paths for fission product radioactivity released within containment. The LCO requires any penetration providing direct access from the containment atmosphere to the outside atmosphere to be closed except for the OPERABLE containment purge and exhaust penetrations and the equipment hatch. For the OPERABLE containment purge and exhaust I penetrations, this LCO ensures that these penetrations are Isolable by the Containment Purge and Exhaust Isolation System. For the equipment hatch, closure capability Is provided by a designated trained hatch closure crew and the necessary equipment. The I OPERABILITY requirements for LCO 3.3.6, "Containment Purge and Exhaust Isolation Instrumentation," ensure that the automatic purge and exhaust valve closure times specified in the FSAR can be (continued)
Farley Units 1 and 2 B 3.9.3-3 Revision
Containment Penetrations B 3.9.3 BASES LCO achieved and, therefore, meet the assumptions used In the safety (continued) analysis to ensure that releases through the valves are terminated, such that radiological doses are within the acceptance limit.
The equipment hatch is considered isolable when the following criteria are satisfied:
- 1. the necessary equipment required to close the hatch is available,
- 2. at least 23 feet of water is maintained over the top of the reactor vessel flange in accordance with Specification 3.9.6,
- 3. a designated trained hatch closure crew Is available.
The equipment hatch opening must be capable of being cleared of any obstruction so that closure can be achieved as soon as possible.
APPLICABILITY The containment penetration requirements are applicable during CORE ALTERATIONS or movement of irradiated fuel assemblies within containment because this is when there is a potential for a fuel handling accident. In MODES 1, 2, 3, and 4, containment penetration requirements are addressed by LCO 3.6.1. In MODES 5 and 6, when CORE ALTERATIONS or movement of irradiated fuel assemblies within containment are not being conducted, the potential for a fuel handling accident does not exist. Therefore, under these conditions no requirements are placed on containment penetration status.
ACTIONS A.1 and A.2 If the containment equipment hatch, air locks, or any containment penetration that provides direct access from the containment atmosphere to the outside atmosphere is not in the required status, Including the Containment Purge and Exhaust Isolation System not capable of automatic actuation when the purge and exhaust valves are open, the unit must be placed in a condition where the isolation function Is not needed. This is accomplished by immediately suspending CORE ALTERATIONS and movement of irradiated fuel assemblies within containment. Performance of these actions shall not preclude completion of movement of a component to a safe position.
Farley Units 1 and 2 B 3.9.3-4 Revision
Containment Penetrations B 3.9.3 BASES SURVEILLANCE SR 3.9.3.1 REQUIREMENTS This Surveillance demonstrates that each of the containment penetrations required to be in Its closed position Is In that position. The Surveillance on the open purge and exhaust valves will demonstrate that the valves are not blocked from closing. Also, the Surveillance will demonstrate that each valve operator has motive power, which will ensure that each valve is capable of being closed by an OPERABLE automatic containment purge and exhaust isolation signal.
The Surveillance is performed every 7 days during CORE ALTERATIONS or movement of irradiated fuel assemblies within containment. The Surveillance Interval is selected to be commensurate with the normal duration of time to complete fuel handling operations. A surveillance before the start of refueling operations will provide two or three surveillance verifications during the applicable period for this LCO. As such, this Surveillance ensures that a postulated fuel handling accident that releases fission product radioactivity within the containment will not result in a release of fission product radioactivity to the environment.
SR 3.9.3.2 This Surveillance demonstrates that each containment purge and exhaust valve actuates to its Isolation position on manual initiation or on an actual or simulated high radiation signal from each of the containment purge radiation monitoring Instrumentation channels.
The 18 month Frequency maintains consistency with other similar ESFAS Instrumentation and valve testing requirements. In LCO 3.3.6, the Containment Purge and Exhaust Isolation instrumentation requires a CHANNEL CHECK every 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> and a COT every 92 days to ensure the channel OPERABILITY during refueling operations. Every 18 months a CHANNEL CALIBRATION is performed. The system actuation response time is demonstrated every 18 months, during refueling, on a.STAGGERED TEST BASIS.
SR 3.6.3.4 demonstrates that the Isolation time of each valve is In accordance with the Inservice Testing Program requirements. These Surveillances performed during MODE 6 will ensure that the valves are capable of closing after a postulated fuel handling accident to limit a release of fission product radioactivity from the containment.
(continued)
Farley Units 1 and 2 B 3.9.3-5 Revision I
Containment Penetrations B 3.9.3 BASES SURVEILLANCE SR 3.9.3.3 REQUIREMENTS The equipment hatch is provided with a set of hardware, tools, and equipment for moving the hatch from Its storage location and installing it in the opening. The required set of hardware, tools, and equipment shall be inspected to ensure that they can perform the required functions.
The 7 day frequency is adequate considering that the hardware, tools, and equipment are dedicated to the equipment hatch and not used for any other functions.
The SR is modified by a Note which only requires that the surveillance be met for an open equipment hatch. Ifthe equipment hatch Is Installed in its opening, the availability of the means to Install the hatch Is not required.
REFERENCES 1. GPU Nuclear Safety Evaluation SE-0002000-001, Rev. 0, May 20, 1988.
- 2. FSAR, Section 15.4.5.
- 3. NUREG-0800, Section 15.7.4, Rev. 1, July 1981.
Farley Units 1 and 2 B 3.9.3-6 Revision