View source for BVY 15-024, Revision of Technical Specifications Bases Pages

{{Adams
| number = ML15086A451
| issue date = 03/25/2015
| title = Revision of Technical Specifications Bases Pages
| author name = Chappell C
| author affiliation = Entergy Nuclear Operations, Inc
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000271
| license number = DPR-028
| contact person = 
| case reference number = BVY 15-024, TAC MF3068
| document type = Letter type:BVY, Technical Specification, Bases Change
| page count = 8
| project = TAC:MF3068
| stage = Other
}}

=Text=
{{#Wiki_filter:Entergy Nuclear Operations, Inc.
Vermont Yankee 320 Governor Hunt Rd Vernon, VT 05354 SEntergy                                                        Tel 802 257 7711 Coley C. Chappell Licensing Manager BVY 15-024 March 25, 2015 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555

==SUBJECT:==
Revision of Technical Specifications Bases Pages Vermont Yankee Nuclear Power Station Docket No. 50-271 License No. DPR-28

==REFERENCE:==
Letter, USNRC to Entergy Nuclear Operations, Inc., "Vermont Yankee Nuclear Power Station - Issuance of Amendment to Renewed Facility Operating License RE: Eliminate Operability Requirements for Secondary Containment when Handling Sufficiently Decayed Irradiated Fuel or a Fuel Cask (TAC NO. MF3068)," NVY 15-013, dated February 12, 2015 (ML14304A588)

==Dear Sir or Madam:==

This letter provides revised Vermont Yankee Nuclear Power Station (VYNPS) Technical Specification (TS) Bases pages. The TS Bases were revised in conjunction with an Amendment to Renewed Facility Operating License DPR-28 issued in the referenced letter.
These changes, processed in accordance with our Technical Specification Bases Control Program (TS 6.7.E), were determined not to require prior NRC approval. The revised Bases pages are provided for your information and for updating and inclusion with your copy of the VYNPS TS. No NRC action is required in conjunction with this submittal.
There are no new regulatory commitments being made in this submittal.
Should you have any questions concerning this submittal, please contact me at 802-451-3374.
Sincerely, Ccc/lAcc

BVY 15-024 / Page 2 of 2

==Attachment:==
: 1.       Revised Technical Specifications Bases Pages (5 pages) cc:     Mr. Daniel H. Dorman Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 Mr. James S. Kim, Project Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 08D15 Washington, DC 20555 USNRC Resident Inspector Mr. Christopher Recchia, Commissioner VT Department of Public Service 112 State Street - Drawer 20 Montpelier, Vermont 05620-2601

BVY 15-024 Docket No. 50-271 Attachment 1 Vermont Yankee Nuclear Power Station Revised Technical Specifications Bases Pages (5 pages)

VYNPS BASES: 3.2.C/4.2.C REACTOR BUILDING VENTILATION ISOLATION AND STANDBY GAS TREATMENT SYSTEM INITIATION APPLICABLE SAFETY ANALYSES,            LCO,  and APPLICABILITY    (continued) instrumentation are implicitly assumed in the safety analyses of References 2, 3, and 4, to initiate        closure of the RBAVSIVs and start           the SGT System to limit offsite      doses.
Reactor building ventilation isolation and Standby Gas Treatment System initiation       instrumentation satisfies        Criterion 3 of 10 CFR 50.36(c) (2) (ii).
The operability of the reactor building ventilation isolation                   and Standby Gas Treatment System initiation            instrumentation is dependent on the operability of the individual instrumentation channel Trip Functions specified in Table 3.2.3.
Each Trip Function must have the required number of operable channels in each trip      system, with their    trip    setpoints within the calculational as-found tolerances specified in plant procedures.               Operation with actual trip       setpoints within calculational as-found tolerances provides reasonable assurance that, under worst case design basis conditions, the associated trip                   will occur within the Trip Settings specified in Table 3.2.3.               As a result,     a channel is considered inoperable if           its  actual trip   setpoint is not within the calculational as-found tolerances specified in plant procedures.                    The actual trip      setpoint is calibrated consistent with applicable setpoint methodology assumptions.
In general, the individual Trip Functions are required to be OPERABLE in RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel (with reactor coolant temperature
> 212'F), during operations with the potential for draining the reactor vessel (OPDRVs) and during movement of recently irradiated fuel assemblies in secondary containment, and during Alteration of the Reactor Core; consistent with the Applicability for the SGT System and secondary containment requirements in Specifications 3.7.B and 3.7.C.                 Trip Functions that have different Applicabilities are discussed below in the individual Trip Functions discussion.
"Recently irradiated"         fuel is defined as fuel that has occupied part of a critical       reactor core within the previous 13 days, i.e.            reactor fuel that has decayed less than 13 days following reactor shutdown.                   This minimum decay period is enforced to maintain the validity                of the Fuel Handling Accident dose consequence analysis.
The specific Applicable Safety Analyses, LCO, and Applicability discussions are listed     below on a Trip Function by Trip Function basis.
: 1.      Low Reactor Vessel Water        Level Low reactor pressure vessel (RPV) water level indicates that the capability to cool the fuel may be threatened.              Should RPV water level decrease too far, fuel damage could result.         An isolation      of the secondary containment and actuation of the SGT System are initiated            in order to minimize the potential of an offsite      release. The Low Reactor Vessel Water Level Trip Function is one of the Trip Functions assumed to be operable and capable of providing isolation and initiation       signals. The isolation and initiation        of systems on Low Reactor Vessel Water Level support actions to ensure that any offsite                  releases are within the limits calculated in the safety analysis.
Low Reactor Vessel Water Level signals are initiated                from level transmitters that sense the difference between the pressure due to a constant column of water (reference leg) and the pressure due to the actual water level (variable leg) in the vessel.         Four channels of Low Reactor Vessel Water Level Trip Function are available and are required to be operable to ensure that no single instrument failure       can preclude the isolation and initiation            function.
Amendment No. 2-34, 262                                                                    76p

VYNPS BASES: 3.2.C/4.2.C REACTOR BUILDING VENTILATION ISOLATION AND STANDBY GAS TREATMENT SYSTEM INITIATION APPLICABLE SAFETY ANALYSES,      LCO, and APPLICABILITY  (continued) have originated from the primary containment due to a break in the RCPB or the refueling floor due to a fuel handling accident.        When High Reactor Building Ventilation Radiation or High Refueling Floor Zone Radiation is detected, secondary containment isolation and actuation of the SGT System are initiated to support actions to limit the release of fission products as assumed in the UFSAR safety analyses (Ref. 4).
The High Reactor Building Ventilation Radiation and High Refueling Floor Zone Radiation signals are initiated from radiation detectors that are located on the ventilation exhaust duct coming from the reactor building and the refueling floor zones, respectively.       Two channels of High Reactor Building Ventilation Radiation Trip Function and two channels of High Refueling Floor Radiation Trip Function are available and are required to be operable to ensure that no single instrument failure can preclude the isolation and initiation function.
The Trip Settings are chosen to promptly detect gross failure of the fuel cladding.
The High Reactor Building Ventilation Radiation and High Refueling Floor Zone Radiation Trip Functions are required to be operable in RUN, STARTUP/HOT STANDBY, HOT SHUTDOWN, Refuel (with reactor coolant temperature > 212'F) where considerable energy exists in the RCS; thus, there is a possibility of pipe breaks resulting in significant releases of radioactive steam and gas.         In COLD SHUTDOWN and Refuel (with reactor coolant temperature < 212'F), the probability and consequences of these events are low due to the RCS pressure and temperature limitations of these Modes; thus, these Trip Functions are not required. In addition, the Trip Functions are also required to be operable during OPDRVs and during movement of recently irradiated fuel assemblies in the secondary containment, and during Alteration of the Reactor Core, because the capability of detecting radiation releases due to fuel failures (due to fuel uncovery or dropped fuel assemblies) must be provided to ensure that offsite dose limits are not exceeded.
"Recently irradiated" fuel is defined as fuel that has occupied part of a critical  reactor core within the previous 13 days, i.e.      reactor fuel that has decayed less than 13 days following reactor shutdown.         This minimum decay period is enforced to maintain the validity of the Fuel Handling Accident dose consequence analysis.
ACTIONS Table 3.2.3 ACTION Note 1 Because of the diversity of sensors available to provide isolation signals and the redundancy of the isolation design, an allowable out of service time of 12 hours or 24 hours depending on the Trip Function (12 hours for those Trip Functions that have channel components common to RPS instrumentation, i.e.,
Trip Functions 1 and 2, and 24 hours for those Trip Functions that do not have channel components common to RPS instrumentation, i.e.,       all other Trip Functions), has been shown to be acceptable (Refs. 5 and 6) to permit restoration of any inoperable channel to operable status.         This out of service time is only acceptable provided the associated Trip Function is still maintaining isolation capability (refer to next paragraph).         If the inoperable channel cannot be restored to operable status within the allowable out of service time, the channel must be placed in the tripped condition per Table 3.2.3 Note l.a.l)      or l.a.2), as applicable. Placing the inoperable channel in trip would conservatively compensate for the inoperability, restore capability to accommodate a single failure, and allow operation to continue.         Alternately, Amendment No. 2-34,  262                                                     76r

VYNPS BASES:    3.7  (Cont'd) surveillances such as monthly torus to drywell vacuum breaker tests.
Procedurally, when AC-6A is open, AC-6 and AC-7 are closed to prevent overpressurization of the SBGT system or the reactor building ductwork, should a LOCA occur.          For this and similar analyses performed, a spurious opening of AC-6 or AC-7 (one of the closed containment isolation valves) is not assumed as a failure simultaneous with a postulated LOCA.       Analyses demonstrate that for normal plant operation system alignments, including surveillances such as those described above, that SBGT integrity would be maintained if a LOCA was postulated.      Therefore, during normal plant operations, the 90 hour clock does not apply.          Accordingly, opening of the 18 inch atmospheric control isolation valves AC-7A, AC-7B, AC-8 and AC-10 will be limited to 90 hours per calendar year (except for performance of the subject valve stroke time surveillances - in which case the appropriate corresponding valves are closed to protect equipment should a LOCA occur). This restriction will apply whenever primary containment integrity is required.          The 90 hour clock will apply anytime purge and vent evolutions can not assure the integrity of the SBGT trains or related equipment.
B. and C. Standby Gas Treatment System and Secondary Containment System The secondary containment is designed to minimize any ground level release of radioactive materials which might result from a serious accident. The Reactor Building provides secondary containment during reactor operation, when the drywell is sealed and in service; the Reactor Building provides primary containment when the reactor is shutdown and the drywell is open, as during refueling.              Because the secondary containment is an integral part of the complete containment system, secondary containment is required at all times that primary containment is required except, however, for initial             fuel loading and low power physics testing.
In the Cold Shutdown condition or the Refuel Mode, the probability and consequences of the LOCA are reduced due to the pressure and temperature limitations in these conditions.              Therefore, maintaining Secondary Containment Integrity is not required in the Cold Shutdown condition or the Refuel Mode, except for other situations for which significant releases of radioactive material can be postulated, such as during operations with a potential for draining the reactor vessel, during alteration of the Reactor Core, or during movement of recently irradiated fuel assemblies in the secondary containment.
           "Recently irradiated" fuel is defined as fuel that has occupied part of a critical    reactor core within the previous 13 days, i.e.          reactor fuel that has decayed less than 13 days following reactor shutdown.              This minimum decay period is enforced to maintain the validity of the Fuel Handling Accident dose consequence analysis.
In order for secondary containment integrity to be met, the secondary containment must function properly in conjunction with the operation of the Standby Gas Treatment System to ensure that the required vacuum can be established and maintained.              This means that the reactor building is intact with at least one door in each access opening closed, and all reactor building automatic ventilation system isolation valves are operable or the affected penetration flow path is isolated.
With the reactor in the Run Mode, the Startup Mode, or the Hot Shutdown condition, if Secondary Containment Integrity is not maintained, Secondary Containment Integrity must be restored within 4 hours.               The 4 hours provides a period of time to correct the problem that is commensurate with the importance of maintaining secondary containment during the Run Mode, the Startup Mode, and the Hot Shutdown condition.
This time period also ensures that the probability of an accident (requiring Secondary Containment Integrity) occurring during periods where Secondary Containment Integrity is not maintained, is minimal.
Amendment No. 4-, 4-43,  4-44, 4-6-,   4-9-4,  262                                     165a

VYNPS BASES:  3.7   (Cont'd)
If Secondary Containment Integrity cannot be restored within the required time period, the plant must be brought to a mode or condition in which the LCO does not apply.
Movement of recently irradiated fuel assemblies in the secondary containment, alteration of the Reactor Core, and operations with the potential for draining the reactor vessel can be postulated to cause fission product release to the secondary containment. In such cases, the secondary containment is the only barrier to release of fission products to the environment. Alteration of the Reactor Core and movement of recently irradiated fuel assemblies must be immediately suspended if Secondary Containment Integrity is not maintained.
Suspension of these activities shall not preclude completing an action that involves moving a component to a safe position. Also, action must be immediately initiated to suspend operations with the potential for draining the reactor vessel to minimize the probability of a vessel draindown and subsequent potential for fission product release.
Actions must continue until operations with the potential for draining the reactor vessel are suspended.
Amendment No. 4-4-3, 4-44, 4-64-, 262                                        165b

VYNPS BASES:  3.7   (Cont'd)
The Standby Gas Treatment System (SGTS) is designed to filter            and exhaust the Reactor Building atmosphere to the stack during secondary containment isolation conditions, with a minimum release of radioactive materials from the Reactor Building to the environs.            To insure that the standby gas treatment system will be effective in removing radioactive contaminates from the Reactor Building air, the system is tested periodically to meet the intent of ANSI N510-1975.             Laboratory charcoal testing will be performed in accordance with ASTM D3803-1989, except, as allowed by GL 99-02, testing can be performed at 70%
relative humidity for systems with humidity control.            Both standby gas treatment fans are designed to automatically start           upon containment isolation and to maintain the Reactor Building pressure to approximately a negative 0.15 inch water gauge pressure; all            leakage should be in-leakage.         Should the fan fail    to start, the redundant alternate fan and filter         system is designed to start   automatically.
Each of the two fans has 100% capacity.           This substantiates the availability of the operable train and results in no added risk; thus, reactor operation or refueling operation can continue.            If neither train is operable, the plant is brought to a condition where the system is not required.
When the reactor is in cold shutdown or refueling the drywell may be open and the Reactor Building becomes the only containment system.
During cold shutdown the probability and consequences of a DBA LOCA are substantially reduced due to the pressure and temperature limitations in this mode.      However, for other situations under which significant radioactive release can be postulated, such as during operations with a potential for draining the reactor vessel, during core alterations, or during movement of recently irradiated fuel in the secondary containment, operability of standby gas treatment is required.
Both trains of the Standby Gas Treatment System are normally operable when secondary containment integrity is required.            However, Specification 3.7.B.3 provides Limiting Conditions for Operation when one train of the Standby Gas Treatment System is inoperable.
Provisional, continued operation is permitted since the remaining operable train is adequate to perform the required radioactivity release control function.           If the applicable conditions of Specification 3.7.B.3 cannot be met, the plant must be placed in a mode or condition where the Limiting Conditions for Operation do not apply.
Entry into a refueling condition with one train of SBGTS inoperable is acceptable and there is no prohibition on mode or condition entry in this situation.        In this case, the requirements of TS 3.7.B.3.b are sufficient to ensure that adequate controls are in place.             During refueling conditions, accident risk is significantly reduced, and the primary activities of concern involve core alterations, movement of recently irradiated fuel assemblies and OPDRVs.
During refueling and cold shutdown conditions Specification 3.7.B.3.b provides for the indefinite continuance of refueling operations with one train of the Standby Gas Treatment System inoperable.             When the seven-day completion time associated with Specification 3.7.B.3.b is not met and secondary containment integrity is required, the operable train of the Standby Gas Treatment System should immediately be placed into operation.        This action ensures that the remaining train is operable, that no failures that could prevent automatic actuation have occurred, and that any other failure would be readily detected.              An alternative to placing the operable train of Standby Gas Treatment in operation is to immediately suspend activities that represent a potential for releasing radioactive material to the secondary containment, thus placing the plant in a condition that minimizes risk.
Amendment No. 4-&, 4-9, 4-4-3,  4*4-, 4-94,   262                                       166}}