View source for BVY 07-056, Technical Specification Proposed Change No. 274, Changes to Technical Specifications for Emergency Diesel Generator Fuel Oil and Reactor Building Crane Surveillance Requirements

{{Adams
| number = ML072970348
| issue date = 10/18/2007
| title = Technical Specification Proposed Change No. 274, Changes to Technical Specifications for Emergency Diesel Generator Fuel Oil and Reactor Building Crane Surveillance Requirements
| author name = Sullivan T
| 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 07-056
| document type = Letter type:BVY, License-Application for Facility Operating License (Amend/Renewal) DKT 50, Technical Specifications
| page count = 20
}}

=Text=
{{#Wiki_filter:Entergy Nuclear Operations, Inc.
P.O. Box 0500
     -                                                             185 Old Ferry Road Brattleboro, VT 05302-0500 Tel 802 257 5271 October 18, 2007 BVY 07-056 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

==Subject:==
Vermont Yankee Nuclear Power Station Docket No. 50-271, License No. DPR-28 Technical Specifications Proposed Change No. 274 Changes to Technical Specifications for Emergency Diesel Generator Fuel Oil and Reactor Building Crane Surveillance Requirements

==Dear Sir or Madam,==

Pursuant to 10CFR50.90, Entergy Nuclear Operations, Inc. (Entergy) is proposing to amend Operating License DPR-28 for Vermont Yankee Nuclear Power Station (VY).                    The proposed changes would revise the Operating License Technical Specifications (TS) to change requirements related to Emergency Diesel Generator (EDG) fuel oil tank volume, EDG fuel oil testing and Reactor Building crane inspections.
Entergy has reviewed the proposed amendment in accordance with 10CFR50.92 and concludes it does not involve a significant hazards consideration. In accordance with 10CFR50.91, a copy of this application, with attachments, was provided to the State of Vermont, Department of Public Service. to this letter provides an evaluation of the proposed change. Attachment 2 contains a markup of the current TS pages and associated Bases. Attachment 3 contains the retyped TS and Bases pages. The TS Bases are provided for information and will be revised following approval of the proposed change in accordance with Vermont Yankee TS Section 6.7.E 'Technical Specifications (TS) Bases Control Program."
To support the timely transition to Ultra-Low-Sulfur Diesel Fuel, Entergy requests approval of the proposed amendment by June 1, 2008 with a 60 day implementation There are no new regulatory commitments made in this letter.
Aco(
OwzR

BVY 07-056 / Page 2 of 2 If you have any questions on this transmittal, please contact Mr. David Mannai at (802) 258-5422.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on October 18, 2007.
Sincerely, Site Vice President Vermont Yankee Nuclear Power Station : Evaluation of the Proposed Changes : Markup of the Current Technical Specifications and Bases Pages : Retyped Technical Specification and Bases Pages cc:     Mr. Samuel J. Collins (w/o attachments)
Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. James S. Kim, Project Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 08C2A Washington, DC 20555 USNRC Resident Inspector Entergy Nuclear Vermont Yankee, LLC P.O. Box 157 Vernon, Vermont 05354 Mr. David O'Brien, Commissioner VT Department of Public Service 112 State Street - Drawer 20 Montpelier, Vermont 05620-2601

BVY 07-056 Docket No. 50-271 Attachment 1 Vermont Yankee Nuclear Power Station Proposed Change 274 Evaluation of the Proposed Changes

BVY 07-056 / Attachment 1 / Page 1 of 8 EVALUATION OF THE PROPOSED CHANGES Description of Chanqes Entergy Nuclear Operations, Inc. (Entergy) is requesting to amend Operating License DPR-28 for Vermont Yankee Nuclear Power Station (VY). The proposed changes revise the Operating License Technical Specifications (TS) to:
: 1) Replace the 36,000 gallon fuel oil tank minimum volume requirement specified in TS 3.10.C with a requirement to maintain a minimum seven (7) day supply of useable diesel fuel recognizing that the 36,000 gallon minimum fuel oil supply requirement is also located in the TS Bases.
: 2) Revise the fuel oil surveillance requirement specified in TS 4.10.C.2 to eliminate the reference to a specific ASTM standard (ASTM D975-02) and replace it with a requirement to sample "in accordance with the applicable ASTM Standards" which are already specified in the TS Bases.
: 3) Revise the reactor building crane surveillance requirements specified in TS 4.12.G to eliminate the reference to the specific ANSI Standard (ANSI B30.2-1967) and replace it with a requirement to inspect "in accordance with the applicable ANSI Standard" and add a reference to the applicable ANSI standard to the TS Bases.
These changes are intended to ensure that the information required by 10CFR50.36 "Technical specifications" is maintained in the TS. However, the specific design value for EDG fuel oil volume that needs to be maintained in the fuel oil storage tank and specific versions of ASTM or ANSI Standards associated with testing of EDG fuel oil and inspection of the Reactor Building Crane are not required to be in the TS per 10CFR50.36 and can be relocated to a licensee controlled document (i.e. the TS Bases). The TS Bases are controlled in accordance with Vermont Yankee TS 6.7.E 'Technical Specification (TS)
Bases Control Program" and 10CFR50.59.
These changes will place Entergy in a better position to efficiently revise the requirements contained in the TS Bases as changes may be needed to address updates to regulations and standards governing EDG fuel oil quality or Reactor Building crane inspection requirements.

BVY 07-056 / Attachment 1 / Page 2 of 8
: 2.      Proposed Changes The following changes are proposed to the current TS (CTS) Section 3.10.C Diesel Fuel, 4.10.C Diesel Fuel and 4.12.G Crane Operability:
CTS 3.10.C                                 Proposed TS 3.10.C There shall be a minimum of 36,000         There shall be a minimum 7 day supply of usable gallons of diesel fuel oil in the   usable diesel fuel oil in the diesel fuel oil diesel fuel oil storage tank.              storage tank.
CTS 4.10.C.2                               Proposed TS 4.10.C.2 Once a month a sample of diesel fuel       Once a month a sample of diesel fuel shall shall be taken and checked for quality,    be taken, checked for quality in accordance The quality shall be within the applicable with the applicable ASTM Standards and limits specified on Table I of ASTM        logged.
D975-02 and logged.
CTS 4.12.G.1.a                             Proposed TS 4.12.G.1 .a Within one month prior to spent fuel cask  Within one month prior to spent fuel cask handling operations, an inspection of      handling operations, an inspection of crane crane cables, sheaves, hook, yoke and      cables, sheaves, hook, yoke and cask lifting cask lifting trunnions will be made. These trunnions will be made in accordance with inspections shall meet the requirements    the applicable ANSI Standard. A crane of ANSI Standard B30.2-1967. A crane       rope shall be replaced if any of the rope shall be replaced if any of the       replacement criteria are met.
replacement criteria given in ANSI B30.2-1967 are met.

BVY 07-056 / Attachment 1 / Page 3 of 8
: 3.      Backqround 3.1      Diesel Fuel Oil Volume Requirements In January 2001 and June 2004, the U.S. Environmental Protection Agency (EPA) finalized the Clean Diesel Trucks and Buses Rule and the Clean Non-road Diesel Rule, respectively with more stringent standards for new diesel engines and fuels.
The processing required to reduce the sulfur in Ultra-Low-Sulfur Diesel Fuel (ULSD) reduces the aromatics content and density of diesel fuel, resulting in a reduction in volumetric energy content (BTU/gallon). The reduced energy capacity of the ULSD may result in increased fuel consumption such that the TS limit on diesel fuel volume would be insufficient to ensure that an Emergency Diesel Generator (EDG) can operate for at least 7 days at a continuous duty rating of 2750 kw.
The Vermont Yankee (VY) licensing basis requires a minimum diesel fuel oil supply of 36,000 gallons be maintained in the fuel oil storage tank to supply one diesel generator for a minimum of 7 days of operation at its continuous duty rating.
The requirements for diesel fuel oil volume may change in the future and the addition of additives to compensate for the issues associated with ULSD discussed in Information Notice 2006-22 "New Ultra-Low-Sulfur Diesel Fuel Oil Could Adversely Impact Diesel Engine Performance," dated October 12, 2006, may further effect the volumetric energy content and as a result the minimum stored volume requirement. These changes could, without this change to the TS, result in future license amendments to revise the stored volume requirements in order to ensure that the volume provides for at least 7 days of diesel generator operation.
In order to facilitate the expeditious revision of the fuel oil volume and testing requirements and to avoid unnecessary expenditure of resources, the proposed change replaces the current specific 36,000 gallon diesel fuel oil volume requirement with a requirement to maintain sufficient volume to support 7 days of EDG operation. The 36,000 gallon minimum diesel fuel oil volume requirement is already specified in the applicable TS Bases.
3.2      Diesel Fuel Oil Testing Requirements The VY licensing basis requires a monthly sample of diesel fuel oil to be taken, checked for quality in accordance with ASTM D975-02 and the results logged.
During the monthly test for quality a viscosity and water sediment test is also performed in accordance with ASTM D975-02. The quality of the diesel fuel oil is considered acceptable if the test results are within the limiting requirements for diesel fuel oils shown on Table 1 of ASTM D975-02.
The requirements for diesel fuel oil testing may change in the future due to the addition of additives to compensate for the issues associated with ULSD discussed in Information Notice 2006-22. These changes, without this change to the TS, could result in future license amendments to revise the stated testing requirements.

BVY 07-056 / Attachment 1 / Page 4 of 8 In order to facilitate the expeditious revision of the fuel oil testing requirements and avoid unnecessary expenditure of resources, the proposed change replaces the
                -current reference to a specific ASTM Standard with a requirement to sample "in accordance with the applicable ASTM Standards" which are already specified in the TS Bases. The proposed change will provide flexibility to update fuel oil testing practices under 10CFR50.59 should there be changes in EPA regulations for fuel oil or newer editions of the ASTM Standards be issued.
3.3      Reactor Building Crane Surveillance Requirements The VY licensing basis requires an inspection to be performed on the Reactor Building Crane within one month prior to spent fuel cask handling. The TS requires that this inspection meet the requirements of ANSI B30.2-1967. In addition, if the replacement criteria in the ANSI Standard are met, the crane rope needs to be replaced.
This change revises TS 4.12.G.1.a to remove reference to the specific ANSI Standard (ANSI B30.2-1967) and replaces it with a requirement to inspect "in accordance with the applicable ANSI Standard" and adds a reference to the applicable ANSI standard in the TS Bases.
The proposed change will provide flexibility to maintain the inspection requirements in accordance with 10CFR50.59 should newer editions of the ANSI Standards be issued. Currently the use of a different ANSI Standard than specified in the TS or a newer edition of the referenced ANSI Standard is not permitted without a license amendment.        In order to facilitate the expeditious revision of the inspection requirements and to avoid unnecessary expenditure of resources, the proposed change eliminates reference to the specific ANSI Standard in the TS since it will be referenced in the supporting TS Bases.
: 4.      Technical Analysis 4.1      Diesel Fuel Oil Volume Requirements The initial conditions of Design Basis Accident (DBA) analyses assume Engineered Safety Feature (ESF) systems are operable. The EDGs are designed to provide sufficient capacity, capability, redundancy and reliability to ensure availability of necessary power to ESF systems so that nuclear fuel, Reactor Coolant System and Primary Containment design limits are not exceeded. To support this mission, an adequate quantity and quality of fuel oil needs to be maintained onsite so that adequate time is available to provide for offsite replenishment.
Each of the EDGs is capable of supplying 100 percent of the minimum emergency loads required under postulated design basis accident conditions. Each EDG is physically and electrically independent from the other and any offsite power source.

BVY 07-056 / Attachment 1 / Page 5 of 8 Each EDGs fuel oil supply consists of an 800 gallon day tank piped directly to the diesel fuel block. Makeup to each EDG day tank is accomplished automatically from a 75,000 gallon fuel storage tank located adjacent to the building that houses the diesel generators. The storage tank is maintained with at least the minimum volume of oil necessary to provide seven days fuel oil supply to an EDG operating at the continuous duty rating of 2750 kw. This onsite fuel oil capacity is sufficient to operate an EDG longer than the time to replenish the onsite supply from offsite sources. Fuel oil is transferred from the storage tank to the day tanks by transfer pumps. The transfer pump motor and automatic controls for the associated day tank receive electrical power from the diesel generator supplied from the respective day tank.
The current volume of fuel oil required to support an EDG operating for 7 days at the continuous rating of 2750 kw is 36,000 gallons. This 36,000 gallon value is stated in both the Technical Specification (TS) and the TS Bases.
This proposed change replaces the 36,000 gallon requirement in the TS with a requirement to maintain a 7 day fuel oil supply. Subsequent changes to the specific volume requirement contained in the TS Bases would be reviewed under 10CFR50.59 to determine if prior NRC approval is required.
Based on this, the proposed TS and supporting TS Bases will continue to ensure that adequate fuel oil is available in the fuel oil storage tank. Therefore, the operability of the EDGs is unaffected.
4.2      Diesel Fuel Oil Testing requirements The initial conditions of Design Basis Accident (DBA) analyses assume Engineered Safety Feature (ESF) systems are operable. The EDGs are designed to provide sufficient capacity, capability, redundancy and reliability to ensure availability of necessary power to ESF systems so that nuclear fuel, Reactor Coolant System and Primary Containment design limits are not exceeded. To support this mission, it is necessary to ensure for proper quality of the fuel oil.
Testing of the fuel oil is currently performed to demonstrate that the requirements specified on Table I of ASTM Standard D975-02 are satisfied. Reference to the ASTM standard is contained in both the TS and the TS Bases.
This proposed change replaces the reference to the specific ASTM Standard in the TS with a requirement to sample "in accordance with the applicable ASTM Standards" which are already specified in the TS Bases. Subsequent changes to the specific testing standard contained in the TS Bases would be reviewed under 10CFR50.59 to determine if prior NRC approval is required.
Since the specific ASTM Standard reference is also included in both the TS and associated TS Bases, removal of the reference to the specific ASTM Standard from the TS will not affect the fuel oil properties and operability of the EDGs will be maintained.

BVY 07-056 / Attachment 1 / Page 6 of 8 Based on this, the proposed TS and supporting TS Bases will continue to ensure that quality fuel oil is used in the EDGs. Therefore the operability of the EDGs is unaffected.
4.3 Reactor Building Crane Surveillance Requirements TS 3.12.G requires the Reactor Building Crane to be operable when the crane is used for handling of a spent fuel cask. To support operability, Surveillance Requirement (SR) 4.12.G.1.a requires that within one month prior to spent fuel cask handling operations, an inspection of crane cables, sheaves, hook, yoke and cask lifting trunnions will be made. The SR requires that these inspections meet the requirements of ANSI Standard B30.2, 1967. In addition, the SR requires the crane rope to be replaced if any of the replacement criteria given in the ANSI standard are met. The operability and surveillance requirements of the Reactor Building Crane ensure that the redundant features of the crane have been adequately inspected just prior to using the crane for handling of a spent fuel cask. The redundant hoist system ensures that a load will not be dropped for any postulated credible single component failure.
This change revises TS 4.12.G.1.a to replace reference to the specific American National Standards Institute (ANSI) Standard (ANSI B30.2-1967) with a requirement to inspect "in accordance with the applicable ANSI Standard." Reference to the specific ANSI Standard will be added to the applicable TS Bases. Once located in the TS Bases, the requirement will be controlled in accordance with TS 6.7.E "Technical Specifications (TS) Bases Control Program" and 10CFR50.59.
The proposed change will provide flexibility to update the inspection requirements in accordance with 10CFR50.59 when newer editions of the ANSI Standards are issued. Currently, the use of a different ANSI Standard than specified in the TS or a newer edition of the referenced ANSI Standard is not permitted without a license amendment. In order to facilitate the expeditious revision of the inspection requirements and to avoid unnecessary expenditure of resources, the proposed change eliminates reference to the ANSI Standard in the TS since it will also be referenced in the supporting TS Bases. This'change, to relocate the reference to a specific ANSI Standard in the TS, is consistent with the change proposed to TS 4.10.C.2 discussed above.
Based on this, the proposed TS and supporting TS Bases will continue to ensure that adequate inspections are performed on the Reactor Building Crane prior to use for spent fuel cask movement. Therefore, the operability of the Reactor Building Crane is unaffected.

BVY 07-056 / Attachment 1 / Page 7 of 8
: 5.      Regulatory Safety Analysis 5.1      No Siqnificant Hazards Consideration Entergy Nuclear Operations, Inc. (Entergy) is proposing to modify the Vermont Yankee Technical Specifications applicability requirements to replace the specific 36,000 minimum gallon of usable diesel fuel volume requirement for the Emergency Diesel Generator fuel oil storage tank with an equivalent Technical Specification requirement to maintain a 7 day supply of fuel oil. The proposed change also replaces the reference to specific ASTM and ANSI Standards, for Emergency Diesel Generator Fuel oil testing and Reactor Building Crane inspections, with a general reference to applicable ASTM or ANSI Standards in the Technical Specifications.
Reference to the specific ASTM or ANSI Standards will be made in the Technical Specification Bases which is controlled under 10CFR50.59 per Vermont Yankee Technical Specification 6.7.E 'Technical Specification (TS) Bases Control Program."
Entergy has evaluated whether or not a significant hazards consideration is involved with the proposed amendment(s) by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:
: 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No. The changes do not impact the operability of any Structure, System or Component that affects the probability of an accident or that supports mitigation of an accident previously evaluated. The proposed change does not affect reactor operations or accident analysis and has no radiological consequences. The operability requirements for accident mitigation systems remain consistent with the licensing and design basis.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
: 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No. The proposed change does not involve any physical alteration of plant equipment and does not change the method by which any safety-related system performs its function. As such, no new or different types of equipment will be installed, and the'operation of installed equipment is unchanged. The methods governing plant operation and testing remain consistent with current safety analysis assumptions.            Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.

BVY 07-056 / Attachment 1 / Page 8 of 8
: 3. Does the proposed change involve a significant reduction in a margin of safety?
Response:      No. The specified margin for onsite fuel oil storage is maintained and the applicable testing standards and methods remain unchanged. These changes do not change any existing requirements, and do not adversely affect existing plant safety margins or the reliability of the equipment assumed to operate in the safety analysis. As such, there are no changes being made to safety analysis assumptions, safety limits or safety system settings that would adversely affect plant safety as a result of the proposed change. Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above, Entergy concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c),
and, accordingly, a finding of "no significant hazards consideration" is justified.
5.2      Environmental Consideration A review has determined that the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.
Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need to be prepared in connection with the proposed amendment.
: 6.      Precedents Vermont Yankee has custom Technical Specifications and a number of changes are proposed in this application. Based on this, adoption of the Technical Specification Task Force (TSTF) Improved Standard Technical Specification travelers, used to provide guidance to support this proposed change, through the CLIIP process, was not proposed.
The proposed changes are similar to those detailed in the TSTF-374-A, Rev. 0 and TSTF-501, Rev. 0.
: 7.      References
: 1.       TSTF-374-A, Rev.0, "Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil"
: 2.       Letter documenting NRC Staff approval of TSTF-374, Rev 0, USNRC to Technical Specification Task Force, dated January 13, 2005
: 3.       TSTF-501, Rev. 0, "Relocate Stored Fuel Oil Volume and Lube Oil Values to Licensee Control"

BVY 07-056 Docket 50-271 Attachment 2 Vermont Yankee Nuclear Power Station Proposed Change 274 Markup of the Current Technical Specifications and Bases Pages

INSERT 1 in accordance with the applicable ASTM Standards INSERT 2 in accordance with the applicable ANSI Standard.
INSERT # 3 Crane inspections and crane rope replacement criteria shall meet the requirements of ANSI Standard B30.2-1967.

VYNPS 3.10  LIMITING CONDITIONS FOR                     4.10 SURVEILLANCE REQUIREMENTS OPERATION
: 4.  .480 V Uninterruptible Power Systems From and after the date that one Uninterruptible Power System or its associated Motor Control Center are made or found to be inoperable for any reason, the requirements of Specification 3.5.A.4 I
shall be satisfied.
: 5. RPS Power Protection From and after the date that one of the two redundant RPS power protection panels on an in-service RPS MG set or alternate power supply is made or found to be inoperable, the associated RPS MG set or alternate supply will be taken out of service until the panel is restored to operable status.
C. Diesel Fuel                                  C. Diesel Fuel
     ~There       shall be a minimum of                    1. The quantity of diesel busable                                                 generator fuel shall be diesel fuel in the       iesel                       logged weekly and after fuel oil storage tank.!                              each operation of the unit.
: 2. Once a month a sample of diesel fuel shall be taken       checked for qualit Sithin    ths Amendment No. 2-&,  44-2-, 4-4G, 244, -r321                                          218

VYNPS 3.12 LIMITING CONDITIONS FOR              4.12 SURVEILLANCE REQUIREMENTS OPERATION F. Fuel Movement                         F. Fuel Movement The reactor shall be shut                 Prior to any fuel handling or down for a minimum of 24                  movement in the reactor core, hours prior to fuel movement              the licensed operator shall within the reactor core.                  verify that the reactor has been shut down for a minimum of 24 hours.
G. Crane Operability                     G. Crane Operability
: 1. The Reactor Building                 1. a. Within one month crane shall be operable                        prior to spent fuel when the crane is used                         cask handling for handling of a spent                        operations, an fuel cask.                                     inspection of crane cables, sheaves, hook, yoke, and cask lifting trunnions be mad**
Swill Ireguir4mcnts   ef ANSII
                                                             * *A      crane rope shall be replaced if any of the replacement criteria are met.
: b. No-load mechanical and electrical tests will be conducted prior to lifting the empty cask from its transport vehicle to verify proper operation of crane controls, brakes and lifting speeds. A functional test of the crane brakes will be conducted each time an empty cask is lifted clear of its transport vehicle.
Amendment No. 2-, 9 -                                                     235

VYNPS BASES:   3.12 & 4.12   (Cont'd)
E. The intent of this specification is to permit the unloading of a portion of the reactor core for such purposes as inservice inspection requirements, examination of the core support plate, control rod, control rod drive maintenance, etc.        This specification provides assurance that inadvertent criticality does not occur during such operation.
This operation is performed with the mode switch in the "Refuel" position to provide the refueling interlocks normally available during refueling as explained in the Bases for Specification 3.12.A.          In order to withdraw more than one control rod, it is necessary to bypass the refueling interlock on each withdrawn control rod which prevents more than one control rod from being withdrawn at a time.         The requirement, that the fuel assemblies in the cell controlled by the control rod be removed from the reactor core before the interlock can be bypassed ensures that withdrawal of another control rod does not result in inadvertent criticality.        Each control rod essentially provides reactivity control for the fuel assemblies in the cell associated with that control rod.       Thus, removal of an entire cell (fuel assemblies plus control rod) results in a lower reactivity potential of the core.
One method available for unloading or reloading the core is the spiral unload/reload. Spiral reloading and unloading encompass reloading or unloading a cell on the edge of a continuous fueled region (the cell can be reloaded or unloaded in any sequence.)        The pattern begins (for reloading) and ends (for unloading) around a single SRM.         The spiral reloading pattern is the reverse of the unloading pattern, with the exception that two diagonally adjacent bundles, which have previously accumulated exposure in-core, and placed next to each of the four SRMs before the actual spiral reloading begins.        The spiral reload can be to either the original configuration or a different configuration.
Additionally, at least 50% of the fuel assemblies to be reloaded into the core shall have previously accumulated a minimum exposure of 1000 Mwd/T to ensure the presence of a minimum neutron flux as described in Bases Section 3.12.B.
F. The intent of this specification is to assure that the reactor core has been shut down for at least 24 hours following power operation and prior to fuel handling or movement.        The safety analysis for the postulated refueling accident assumed that the reactor had been shut down for 24 hours for fission product decay prior to any uel handling which could result in dropping of a fuel assembly.                       3 G. The operability requirements of the reactor uilding crane ensures that the redundant features of the crane have een adequately inspected just prior to using it for handling of a sp t fuel cask.         The redundant hoist system ensures that a load wil not be dropped for any postulated credible single component failures.       Details of the design of the redundant features of the crane and specific testing requirements for the crane are delineated in the Vermont Yankee document entitled "Reactor Building Crane Modification" (December 1975).
H. The Spent Fuel Pool Cooling System is designed to maintain the pool water temperature below 125'F during normal refueling operations.          If the reactor core is completely discharged, the temperature of the pool water may increase to greater than 125'F.       The RHR System supplemental fuel pool cooling may be used under these conditions to maintain the pool water temperature less than 150'F.
Amendment No.            *9,
                         ,-4-3-,
q4,   4-8,                                            239

BVY 07-056 Docket 50-271 Attachment 3 Vermont Yankee Nuclear Power Station Proposed Change 274 Retyped Technical Specification andBases Pages

VYNPS 3.10  LIMITING CONDITIONS FOR                     4.10 SURVEILLANCE REQUIREMENTS OPERATION
: 4. 480 V Uninterruptible Power Systems From and after      the date that one Uninterruptible Power System or its associated Motor Control Center are made or found to be inoperable for any reason, the requirements of Specification 3.5.A.4 shall be satisfied.
: 5. RPS Power Protection From and after      the date that one of the two redundant RPS power protection panels on an in-service RPS MG set or alternate power supply is made or found to be inoperable, the associated RPS MG set or alternate supply will be taken out of service until   the panel is restored to operable status.
C. Diesel Fuel                                  C. Diesel Fuel There shall be a minimum 7                       1. The quantity of diesel day supply of usable diesel                           generator fuel shall be fuel in the diesel fuel oil                           logged weekly and after storage tank.                                         each operation of the unit.
: 2. Once a month a sample of diesel fuel shall be taken, checked for quality in accordance with the applicable ASTM Standards and logged.
Amendment No. ,   , 4-89, 2-1-4,2-21                                          218

VYNPS 3.12 LIMITING CONDITIONS FOR               4.12 SURVEILLANCE REQUIREMENTS OPERATION F. Fuel Movement                         F. Fuel Movement The reactor shall be shut                 Prior to any fuel handling or down for a minimum of 24                  movement in the reactor core, hours prior to fuel movement              the licensed operator shall within the reactor core.                  verify that the reactor has been shut down for a minimum of 24 hours.
G. Crane Operability                     G. Crane Operability
: 1. The Reactor Building                  1. a. Within one month crane shall be operable                         prior to spent fuel when the crane is used                          cask handling for handling of a spent                         operations, an fuel cask.                                      inspection of crane cables, sheaves, hook, yoke, and cask lifting   trunnions will be made in accordance with the applicable ANSI Standard. A crane rope shall be replaced if any of the replacement criteria    are met.
: b. No-load mechanical and electrical tests will be conducted prior to lifting     the empty cask from its transport vehicle to verify proper operation of crane controls, brakes and lifting   speeds. A functional test of the crane brakes will be conducted each time an empty cask is lifted    clear of its   transport vehicle.
Amendment No. 9, 2-942                                                          235

VYNPS BASES:  3.12 & 4.12      (Cont'd)
E. The intent of this specification is to permit the unloading of a portion of the reactor core for such purposes as inservice inspection requirements, examination of the core support plate, control rod, control rod drive maintenance, etc.          This specification provides assurance that inadvertent criticality does not occur during such operation.
This operation is performed with the mode switch in the "Refuel" position to provide the refueling interlocks normally available during refueling as explained in the Bases for Specification 3.12.A.            In order to withdraw more than one control rod, it is necessary to bypass the refueling interlock on each withdrawn control rod which prevents more than one control rod from being withdrawn at a time.           The requirement that the fuel assemblies in the cell controlled by the control rod be removed from the reactor core before the interlock can be bypassed ensures that withdrawal of another control rod does not result in inadvertent criticality.          Each control rod essentially provides reactivity control for the fuel assemblies in the cell associated with that control rod.        Thus, removal of an entire cell (fuel assemblies plus control rod) results in a lower reactivity potential of the core.
One method available for unloading or reloading the core is the spiral unload/reload.       Spiral reloading and unloading encompass reloading or unloading a cell on the edge of a continuous fueled region (the cell can be reloaded or unloaded in any sequence.)          The pattern begins (for reloading) and ends (for unloading) around a single SRM.           The spiral reloading pattern is the reverse of the unloading pattern, with the exception that two diagonally adjacent bundles, which have previously accumulated exposure in-core, and placed next to each of the four SRMs before the actual spiral reloading begins.          The spiral reload can be to either the original configuration or a different configuration.
Additionally, at least 50% of the fuel assemblies to be reloaded into the core shall have previously accumulated a minimum exposure of 1000 Mwd/T to ensure the presence of a minimum neutron flux as described in Bases Section 3.12.B.
F. The intent of this specification is to assure that the reactor core has been shut down for at least 24 hours following power operation and prior to fuel handling or movement.          The safety analysis for the postulated refueling accident assumed that the reactor had been shut down for 24 hours for fission product decay prior to any fuel handling which could result in dropping of a fuel assembly.
G. The operability requirements of the reactor building crane ensures that the redundant features of the crane have been adequately inspected just prior to using it for handling of a spent fuel cask.           The redundant hoist system ensures that a load will not be dropped for any postulated credible single component failures.          Crane inspections and crane rope replacement criteria shall meet the requirements of ANSI Standard B30.2-1967.       Details of the design of the redundant features of the crane and specific testing requirements for the crane are delineated in the Vermont Yankee document entitled "Reactor Building Crane Modification" (December 1975).
H. The Spent Fuel Pool Cooling System is designed to maintain the pool water temperature below 125&deg;F during normal refueling operations.            If the reactor core is completely discharged, the temperature of the pool water may increase to greater than 125 0 F.        The RHR System supplemental fuel pool cooling may be used under these conditions to maintain the pool water temperature less than 150'F.
Amendment No. 2-9,--34,    4, *-7, 1-8-1,
                           --              243                                           239}}