ML14084A384
| ML14084A384 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 03/13/2014 |
| From: | Mark D. Sartain Dominion Energy Kewaunee |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 13-226G | |
| Download: ML14084A384 (14) | |
Text
Dominion Energy Kewaunee, Inc.
o 5000 Dominion Boulevard, Glen Allen, VA 23060 Dominion Web Address: www.dom.com March 13, 2014 U. S. Nuclear Regulatory Commission Serial No. 13-226G Attention: Document Control Desk LIC/JG/RO Washington, DC 20555-0001 Docket No. 50-305 License No. DPR-43 DOMINION ENERGY KEWAUNEE, INC.
KEWAUNEE POWER STATION SUPPLEMENT 3: LICENSE AMENDMENT REQUEST 256, PERMANENTLY DEFUELED LICENSE AND TECHNICAL SPECIFICATIONS By application dated May 29, 2013 (Reference 1), Dominion Energy Kewaunee, Inc.
(DEK), requested an amendment to Renewed Facility Operating License Number DPR-43 (Operating License) for Kewaunee Power Station (KPS). The proposed amendment would revise the KPS Operating License and Technical Specifications (TS) to Permanently Defueled Technical Specifications (PDTS),
consistent with the permanently defueled status of the plant. The application was supplemented by letters dated October 15, 2013 (Reference 2) and January 7, 2014 (Reference 3).
In the KPS Post-Shutdown Decommissioning Activities Report (PSDAR) submitted on February 26, 2013, DEK indicated that all irradiated fuel would be transferred to dry storage in the independent spent fuel storage installation (ISFSI) by the end of 2020.
However, DEK recently outsourced activities associated with the transfer of spent fuel remaining in the spent fuel pool to the ISFSI and compressed the schedule for completing the transfer of all spent fuel to the ISFSI. Under the new schedule, DEK expects to have all spent fuel transferred to the ISFSI by the end of 2016.
As recently discussed with NRC staff (Reference 4), scheduled transfers of spent fuel from the spent fuel pool to dry casks are predicated on deletion of certain TS sections as proposed in our original PDTS submittal (Reference 1).
If not deleted, these TS sections would require restoring operability of certain equipment during spent fuel movement that is no longer needed for accident mitigation.
Under the new offload schedule, DEK plans to begin spent fuel transfers to the ISFSI by July 1, 2014. To support these scheduled spent fuel transfers, DEK requests expedited deletion of these specific TS sections in advance of approval of Reference 1.
Additionally, the NRC staff requested changes (Reference 5) to certain portions of the proposed Technical Specifications regarding TS 5.2.2, "Facility Staff," that are associated with spent fuel movement. Accordingly, proposed changes addressing this concern are included in this supplement as well.
Serial No. 13-226G LAR 256 Supplement 3 Page 2 of 3 to this letter provides a supplement to the proposed amendment listing the specific TS sections for which expedited deletion is being requested. This supplement to the proposed amendment also addresses the staffs requested changes to TS 5.2.2.
The conclusions of the no significant hazards consideration and the environmental considerations contained in Reference 1 are not affected by, and remain applicable to, this supplement. provides a markup of the TS Table of Contents reflecting the proposed deletions and a markup of the TS pages reflecting the proposed changes to TS 5.2.2.
To support the scheduled transfers of spent fuel to the ISFSI, deletion of the listed TS sections is requested by June 1, 2014, which was the originally requested approval date for Reference 1.
Please contact Mr. Jack Gadzala at 920-388-8604 if you have any questions or require additional information.
Sincerely, Mark D. Sartain Vice President - Nuclear Engineering COMMONWEALTH OF VIRGINIA
)
COUNTY OF HENRICO The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by Mark D. Sartain, who is Vice President -
Nuclear Engineering of Dominion Energy Kewaunee, Inc.
He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of his knowledge and belief.
Acknowledged before me this 1 '3k day of MA re.
,2014.
My Commission Expires: "D'e-,.6w 31,.. I4 Nota
_blic CRAIG D SLY Attachments:
Notary Public I
Commonwealth of Virginia
- 1. Discussion of Change and Technical Analysis l
Reg. # 7518653 'e t
.My Commission Expires December 31, 20J.6
- 2. Marked Up Technical Specifications Pages I -- ------------------ I
Serial No. 13-226G LAR 256 Supplement 3 Page 3 of 3
References:
- 1. Letter from Eugene S. Grecheck (DEK) to NRC Document Control Desk, "License Amendment Request 256, Permanently Defueled License and Technical Specifications," dated May 29, 2013 (ADAMS Accession No. ML13156A037)
- 2. Letter from Mark D. Sartain (DEK) to NRC Document Control Desk, "Supplement 1 and Response to Request for Additional Information Regarding License Amendment Request 256, Permanently Defueled License and Technical Specifications," dated October 15, 2013 (ADAMS Accession No. ML13294A091)
- 3. Letter from Mark D. Sartain (DEK) to NRC Document Control Desk, "Supplement 2:
License Amendment Request 256, Permanently Defueled License and Technical Specifications," dated January 7, 2014
- 4. Teleconference between NRC staff and DEK representatives, regarding expedited approval of certain portions of Kewaunee Power Station Permanently Defueled Technical Specifications, on January 24, 2014
- 5. Email from Mr. William Huffman (NRC) to Jack Gadzala (DEK) et al, "Draft RAI on Kewaunee Permanently Defueled Technical Specifications," dated March 6, 2014 cc:
Regional Administrator, Region III U. S. Nuclear Regulatory Commission 2443 Warrenville Road Suite 210 Lisle, IL 60532-4352 Mr. W. C. Huffman Jr, Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08-D15 11555 Rockville Pike Rockville, MD 20852-2738 Mr. Christopher Gratton, Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08-D15 11555 Rockville Pike Rockville, MD 20852-2738 Public Service Commission of Wisconsin Electric Division P.O. Box 7854 Madison, WI 53707
Serial No. 13-226G ATTACHMENT I SUPPLEMENT 3:
LICENSE AMENDMENT REQUEST 256 PERMANENTLY DEFUELED LICENSE AND TECHNICAL SPECIFICATIONS DISCUSSION OF CHANGE AND TECHNICAL ANALYSIS KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.
Serial No. 13-226G Page 1 of 5 SUPPLEMENT 3 LICENSE AMENDMENT REQUEST 256 PERMANENTLY DEFUELED LICENSE AND TECHNICAL SPECIFICATIONS DISCUSSION OF CHANGE AND TECHNICAL ANALYSIS
1.0 DESCRIPTION
By application dated May 29, 2013 (Reference 1), Dominion Energy Kewaunee, Inc.
(DEK), requested an amendment to Renewed Facility Operating License Number DPR-43 (Operating License) for Kewaunee Power Station (KPS). The proposed amendment would revise the KPS Operating License and Technical Specifications (TS) to Permanently Defueled Technical Specifications (PDTS),
consistent with the permanently defueled status of the plant. The application was supplemented by letters dated October 15, 2013 (Reference 2) and January 7, 2014 (Reference 3).
In the KPS Post-Shutdown Decommissioning Activities Report (PSDAR) submitted on February 26, 2013, DEK indicated that all irradiated fuel would be transferred to dry storage in the ISFSI by the end of 2020. However, DEK recently outsourced activities associated with the transfer of spent fuel remaining in the spent fuel pool to the independent spent fuel storage installation (ISFSI) and compressed the schedule for completing the transfer of all spent fuel to the ISFSI. Under the new schedule, DEK expects to have all spent fuel transferred to the ISFSI by the end of 2016.
As recently discussed with NRC staff (Reference 4), scheduled transfers of spent fuel from the spent fuel pool to dry casks are predicated on deletion of certain TS sections as proposed in our original PDTS submittal (Reference 1).
If not deleted, these TS sections would require restoring operability of certain equipment during spent fuel movement that is no longer needed for accident mitigation.
Under the new offload schedule, DEK plans to begin spent fuel transfers to the ISFSI by July 1, 2014. To support these scheduled spent fuel transfers, DEK requests expedited deletion of these specific TS sections in advance of approval of Reference 1.
Additionally, the NRC staff requested changes (Reference 5) to certain portions of the proposed Technical Specifications regarding TS 5.2.2, "Facility Staff," that are associated with spent fuel movement. The staff's request stated the following:
Proposed TS 5.2.2 does not require the radiation protection staff to be onsite during fuel handling operations or during movements of loads over storage racks containing fuel. The NRC staff does not find this proposed change to be acceptable for a defueled reactor plant, as it is currently proposed. Please provide a requirement that is consistent with both draft NUREG-1625 and Millstone Unit 1 TSs or provide a technical basis for not maintaining consistency
Serial No. 13-226G Page 2 of 5 with Millstone Unit 1 TSs, since you stated that you would maintain consistency with Millstone Unit 1 in your response dated October 15, 2013.
This supplement to the proposed amendment lists the specific TS sections (that are no longer needed) for which expedited deletion is being requested. This supplement to the proposed amendment also addresses the staffs requested changes to TS 5.2.2. The conclusions of the no significant hazards consideration and the environmental considerations contained in Reference 1 are not affected by, and remain applicable to, this supplement.
2.0 PROPOSED CHANGE
TS Sections Requested for Deletion on an Expedited Basis The original amendment request (Reference 1) proposed deletions of certain Technical Specifications (TS) sections that were no longer needed for the permanently defueled condition. The TS sections shown below are a subset of the TS sections that were originally proposed for deletion. The TS sections listed below are being proposed for deletion separately, in advance of approval of the originally proposed amendment request.
A mark-up of the TS Table of Contents, reflecting the proposed deletions, is provided in.
TS Being Deleted (Expedited Request) 3.3 INSTRUMENTATION 3.3.5 Loss of Offsite Power (LOOP) Diesel Generator (DG) Start Instrumentation 3.3.7 Control:Room Post Accident Recirculation (CRPAR) System Actuation Instrumentation 3.7 PLANT SYSTEMS 317.10 Control Room Post Accident Recirculation (CRPAR) System 3.7.11 Control Room Air Conditioning (CRAC) Alternate Cooling System 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources - Shutdown
.3.8.3 Diesel Fuel Oil and Lube Oil 3.8.5 DC Sources - Shutdown.
3.8.6 Battery Parameters 3.8.8 Inverters - Shutdown 3.8.10 Distribution Systems - Shutdown
Serial No. 13-226G Page 3 of 5 Technical Specifications Section 5.2.2, "Facility Staff" The NRC staff requested changes (Reference 5) to certain portions of the proposed Technical Specifications.
Specifically, the staff requested that DEK provide a requirement for radiation protection staff to be onsite during fuel handling operations or movements of loads over storage racks containing fuel.
In response to the staff's comments, DEK is revising the originally proposed amendment. A specific formal TS for radiation protection staff to be onsite during fuel handling operations or movements of loads over storage racks containing fuel is being added to the TS. contains the marked-up TS page affected by this revision.
The conclusions of the no significant hazards consideration and the environmental considerations contained in Reference 1 are not affected by, and remain applicable to, this revision.
3.0 TECHNICAL ANALYSIS
TS Sections Requested for Deletion on an Expedited Basis No new changes are being proposed in this supplemental request. DEK is requesting expedited approval to delete a specific subset of Technical Specifications (TS) that were proposed for deletion in the original amendment request. The TS proposed for deletion on an expedited basis are those that would unnecessarily require restoring operability of certain equipment during spent fuel movement that is no longer needed for accident mitigation in the spent fuel pool and thereby negatively affect the current schedule for transferring fuel to the ISFSI. Therefore, DEK is requesting NRC approve deletion of the above listed TS sections separately and in advance of the originally proposed change. The technical justification for deleting these TS remains unchanged from that provided in LAR 256 (Reference 1).
In general, because 10 CFR 50.82(a)(2) prohibits operation of the plant or placing fuel in the reactor vessel, the above listed TS are no longer needed to assure the appropriate functional capability of their associated systems, structures, or components (SSCs) for safe operation of the facility. The only remaining Applicability requirement of these TS is "during movement of irradiated fuel assemblies."
The design basis accidents and transients analyzed in USAR Chapter 14 are no longer applicable in the permanently defueled condition, with the exception of the fuel handling accident (FHA) in the auxiliary building (as discussed in Section 5.2, "Applicable Regulatory Requirements/Criteria," of Reference 1). A description of the FHA analysis for the permanently defueled condition is provided in Section 2.0, "Proposed Change,"
of Reference 1. The FHA analysis shows that the dose consequences are acceptable
Serial No. 13-226G Page 4 of 5 without relying on any SSCs to remain functional during and following the event (based on compliance with the spent fuel pool water level requirements of TS 3.7.13).
TS 5.2.2, "Facility Staff" A new, more restrictive change is being proposed in this request. A new requirement is being added for an individual qualified in radiation protection procedures to be onsite during fuel handling operations or movements of loads over storage racks containing fuel. This requirement is consistent with existing TS 5.2.2.d, approved by the NRC for Millstone Unit 1 and consistent with draft NUREG-1625, "Proposed Standard Technical Specifications for Permanently Defueled Westinghouse Plants."
A load is defined as a mass or weight suspended from the crane's hook (e.g., the lifting assembly itself would not be considered a load).
For administrative convenience, this new requirement will be added as TS 5.2.2.e and replace the previous TS 5.2.2.e, whose deletion is described in LAR 256 (Reference 1).
This maintains sequential numbering of the specifications in this section.
DEK believes that it is prudent to have an individual qualified in radiation protection procedures on site during fuel handling operations or movements of loads over storage racks containing fuel.
Accordingly, existing KPS procedures require that radiation protection staff be present for various activities that may affect radiological conditions, such as movement of irradiated fuel. This new TS requirement will provide additional administrative controls for ensuring that an individual qualified in radiation protection procedures on site during fuel handling operations or movements of loads over storage racks containing fuel.
4.0
SUMMARY
Kewaunee Power Station is a permanently defueled facility that has been shutdown for a sufficiently long period of time such that the systems, structures, and components (SSCs) subject to the above listed Technical Specifications (TS) sections are no longer required to address a design basis accident or transient analyses. Therefore, 10 CFR 50.36 no longer requires these SSCs to be included within TS.
Deletion of the above listed TS sections is needed allow transfer of irradiated fuel from the spent fuel pool to the ISFSI in accordance with the schedule that has been established and without unnecessary expenditures of decommissioning trust funds for support of SSCs that are no longer significant to public health and safety.
The revision being proposed in this supplement to TS 5.2.2, "Facility Staff," ensures appropriate requirements for administrative controls in this area.
Serial No. 13-226G Page 5 of 5
5.0 REGULATORY ANALYSIS
5.1 No Significant Hazards Consideration The conclusions of the no significant hazards consideration contained in Reference 1 are not affected by, and remain applicable to, this proposed change.
5.2 Applicable Regulatory Requirements/Criteria The applicable regulatory requirements/criteria contained in Reference 1 are not affected by, and remain applicable to, this proposed change.
6.0 ENVIRONMENTAL CONSIDERATION
The conclusions of the environmental considerations contained in Reference 1 are not affected by, and remain applicable to, this proposed change.
7.0 REFERENCES
- 1. Letter from Eugene S. Grecheck (DEK) to NRC Document Control Desk, "License Amendment Request 256, Permanently Defueled License and Technical Specifications," dated May 29, 2013 (ADAMS Accession No. ML13156A037)
- 2. Letter from Mark D. Sartain (DEK) to NRC Document Control Desk, "Supplement 1 and
Response
to Request for Additional Information Regarding License Amendment Request 256, Permanently Defueled License and Technical Specifications," dated October 15, 2013 (ADAMS Accession No. ML13294A091)
- 3. Letter from Mark D. Sartain (DEK) to NRC Document Control Desk, "Supplement 2:
License Amendment Request 256, Permanently Defueled License and Technical Specifications," dated January 7, 2014
- 4. Teleconference between NRC staff and DEK representatives, regarding expedited approval of certain portions of Kewaunee Power Station Permanently Defueled Technical Specifications, on January 24, 2014
- 5. Email from Mr. William Huffman (NRC) to Jack Gadzala (DEK) et al, "Draft RAI on Kewaunee Permanently Defueled Technical Specifications," dated March 6, 2014
Serial No. 13-226G ATTACHMENT 2 SUPPLEMENT 3:
LICENSE AMENDMENT REQUEST 256 PERMANENTLY DEFUELED LICENSE AND TECHNICAL SPECIFICATIONS MARKED UP TECHNICAL SPECIFICATIONS PAGES (TABLE OF CONTENTS AND TS 5.2.2)
KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.
TABLE OF CONTENTS Page Number 1.0 USE AND APPLICATION 1.1 D e fin itio n s............................................................................................................
1.1 -1 1.2 Log ical C onnecto rs.............................................................................................
1.2-1 1.3 Completion Times 1.3-1 1.4 F re q u e n c y...........................................................................................................
1.4 -1 2.0 S A F E T Y LIM IT S (S Ls)..............................................................................................
2.0-1 2.1 SLs 2.2 SL Violations 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY.......................... 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY.........................................
3.0-4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDO W N M A RG IN (SDM )..........................................................................
3.1.1-1 3.1.2 C o re R e a ctivity.................................................................................................
3.1.2-1 3.1.3 Moderator Temperature Coefficient (MTC).......................................................
3.1.3-1 3.1.4 R od G roup A lignm ent Lim its.............................................................................
3.1.4-1 3.1.5 Shutdow n Bank Insertion Lim its........................................................................
3.1.5-1 3.1.6 C ontrol Bank Insertion Lim its............................................................................
3.1.6-1 3.1.7 R od P osition Indication.....................................................................................
3.1.7-1 3.1.8 PHYSICS TESTS Exceptions - MODE 2..........................................................
3.1.8-1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))...............................................................
3.2.1-1 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FNH)
............................................ 3.2.2-1 3.2.3 AXIAL FLUX DIFFERENCE (AFD)...................................................................
3.2.3-1 3.2.4 QUADRANT POWER TILT RATIO (QPTR)......................................................
3.2.4-1 3.3 INSTRUMENTATION 3.3.1 Reactor Protection System (RPS) Instrumentation...........................................
3.3.1-1 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation......... 3.3.2-1 3.3.3 Post Accident Monitoring (PAM) Instrumentation..............................................
3.3.3-1 3.3.4 Dedicated Shutdow n System............................................................................
3.3.4-1 I 3.3.5 Deleted ss of Offsite Power (LOOP) Diesel Ger_. ator (DG) Start I+- +.rum
+tation3.
3.3.6 Containment Purge and Vent Isolation Instrumentation....................................
3.3.6-1 3.3.7 Deleted.onto Rom Post Ac.ide. t Recirculation (CRPAR) System A ctu -ton Instrum entatioon...........................................................................
3.3.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate B oiling (D N B ) Lim its....................................................................................
3.4.1-1 3.4.2 RCS Minimum Temperature for Criticality.........................................................
3.4.2-1 3.4.3 RCS Pressure and Temperature (P/T) Limits...................................................
3.4.3-1 3.4.4 RC S Loops - M O DES 1 and 2..........................................................................
3.4.4-1 3.4.5 R C S Loops - M O D E 3.....................................................................................
3.4.5-1 3.4.6 R C S Loops - M O D E 4.....................................................................................
3.4.6-1 I Kewaunee Power Station Amendment No. 2-W
TABLE OF CONTENTS Page Number 3.4 REACTOR COOLANT SYSTEM (RCS) (continued) 3.4.7 RCS Loops - MODE 5, Loops Filled.................................................................
3.4.7-1 3.4.8 RCS Loops - MODE 5, Loops Not Filled...........................................................
3.4.8-1 3.4.9 P re ss u rize r.......................................................................................................
3.4.9 -1 3.4.10 Pressurizer Safety Valves...............................................................................
3.4.10-1 3.4.11 Pressurizer Power Operated Relief Valves (PORVs)......................................
3.4.11-1 3.4.12 Low Temperature Overpressure Protection (LTOP) System...........................
3.4.12-1 3.4.13 RCS Operational LEAKAGE...........................................................................
3.4.13-1 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage.................................................
3.4.14-1 3.4.15 RCS Leakage Detection Instrumentation........................................................
3.4.15-1 3.4.16 RCS Specific Activity......................................................................................
3.4.16-1 3.4.17 Steam Generator (SG) Tube Integrity.............................................................
3.4.17-1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.1 A ccu m u lato rs....................................................................................................
3.5.1-1 3.5.2 ECCS - Operating.............................................................................................
3.5.2-1 3.5.3 ECCS - Shutdown............................................................................................
3.5.3-1 3.5.4 Refueling W ater Storage Tank (RW ST)............................................................
3.5.4-1 3.6 CONTAINMENT SYSTEMS 3.6.1 C o nta in m e nt.....................................................................................................
3.6.1-1 3.6.2 Containment Air Locks......................................................................................
3.6.2-1 3.6.3 Containment Isolation Valves...........................................................................
3.6.3-1 3.6.4 Containment Pressure......................................................................................
3.6.4-1 3.6.5 Containment Air Temperature...........................................................................
3.6.5-1 3.6.6 Containment Spray and Cooling Systems........................................................
3.6.6-1 3.6.7 Spray Additive System......................................................................................
3.6.7-1 3.6.8 S hie ld B uild ing..................................................................................................
3.6.8-1 3.6.9 Vacuum Relief Valves......................................................................................
3.6.9-1 3.6.10 Shield Building Ventilation System (SBVS).....................................................
3.6.10-1 3.7 PLANT SYSTEMS 3.7.1 Main Steam Safety Valves (MSSVs).................................................................
3.7.1-1 3.7.2 Main Steam Isolation Valves (MSIVs)...............................................................
3.7.2-1 3.7.3 Main Feedwater Isolation Valves (MFIVs), Main Feedwater Regulation Valves (MFRVs), and MFRV Bypass Valves...............................................
3.7.3-1 3.7.4 Steam Generator (SG) Power Operated Relief Valves (PORVs)...................... 3.7.4-1 3.7.5 Auxiliary Feedwater (AFW ) System..................................................................
3.7.5-1 3.7.6 Condensate Storage Tanks (CSTs)..................................................................
3.7.6-1 3.7.7 Component Cooling (CC) System.....................................................................
3.7.7-1 3.7.8 Service W ater (SW ) System.............................................................................
3.7.8-1 3.7.9 Ultimate Heat Sink (UHS).................................................................................
3.7.9-1 3.7.10 DeletedCntrotl Room Poet Accid;nt Re.ir.l.tion (CRPAR) System.......3*.7.1 3.7.11 DeletedControl Room AFir Conditioning (CRAC) Alternate C*oolng System,.-
3.7.11 1 3.7.12 Auxiliary Building Special Ventilation (ASV) System.......................................
3.7.12-1 3.7.13 Spent Fuel Pool W ater Level..........................................................................
3.7.13-1 3.7.14 Spent Fuel Pool Boron Concentration.............................................................
3.7.14-1 3.7.15 Spent Fuel Pool Storage.................................................................................
3.7.15-1 3.7.16 Secondary Specific Activity.............................................................................
3.7.16-1 Kewaunee Power Station ii Amendment No. 2-W
TABLE OF CONTENTS (continued)
Page Number 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources - O perating....................................................................................
3.8.1-1 3.8.2 DeletedAC Sou-rces Shutdown 3.8.2 3.8.3 DeletedDiesel Fuel Oil and L'ube Oil..................................
8.3 1 3.8.4 DC Sources - O perating...................................................................................
3.8.4-1 3.8.5 DeletedDC S u-rces Shutdown...................................................................
3.8.5 1 3.8.6 DeletedBattery Param etters..............................................................................
3.8. 1 3.8.7 Inverters - O perating.........................................................................................
3.8.7-1 3.8.8 Deltedl
.'.e.t..
Shutd wn............................................................................
3.8.8 1 3.8.9 Distribution System s - O perating......................................................................
3.8.9-1 3.8.10 Delete DiS...
SyStem.
ShutdoWn...............................
.......................... 3.8.10. 1 3.9 REFUELING OPERATIONS 3.9.1 Boron Concentration.........................................................................................
3.9.1-1 3.9.2 Nuclear Instrum entation....................................................................................
3.9.2-1 3.9.3 Residual Heat Removal (RHR) and Coolant Circulation - High Water Level.... 3.9.3-1 3.9.4 Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level..... 3.9.4-1 3.9.5 Refueling Cavity W ater Level............................................................................
3.9.5-1 3.9.6 Containm ent Penetrations................................................................................
3.9.6-1 4.0 DESIG N FEATURES................................................................................................
4.0-1 4.1 Site Location........................................................................................................
4.0-1 4.2 Reactor Core......................................................................................................
4.0-1 4.3 Fuel Storage.......................................................................................................
4.0-1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility......................................................................................................
5.1-1 5.2 O rganization........................................................................................................
5.2-1 5.3 Unit Staff Q ualifications.......................................................................................
5.3-1 5.4 Procedures..........................................................................................................
5.4-1 5.5 Program s and M anuals........................................................................................
5.5-1 5.6 Reporting Requirem ents......................................................................................
5.6-1 5.7 High Radiation Area............................................................................................
5.7-1 I Kewaunee Power Station iii Amendment No. 2-07
Organization 5.2 5.2 Organization NOTE: Changes to TS 5.2.2.c and d, along with deletion of the original TS 5.2.2.e are justified separately in LAR 256.
1 5.2.2 UPAit-FgacilytStaff (continued)
C.
d.
e.
A radiation technolHl*1 t shall be On site when fuel i* i* the rea*ct*. The pos~ition m~ay be vacant for no-t mo-re than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, except in severe weathe conditone, in order to provido for unexpected aben, pro.ided immediate aet"On is takon to fill the.eq d
.*.eposition. All fuel handling operations shall be directly supervised by a qualified individual.
The epeafiens shift manager or assistant operations manager shall 4GkL-e a CERTIFIED FUEL HANDLERSenio,!r O
.perato licen e.
W~hen the unit is i MORVGDE 1, 2, 3, or 4 an iniiulsalprovide advisor,'
technical support to the unit operations, s-hift c-row. in the arears of the~rmal hydraulics, reactor ongineering, and plant analysis With regard to the safe operation of the unit. This, individua! shall mneet the qualifications spocifid by the Commission Policy Statemnent On EnRgineedrig Expertfise on Shfift.An individual qualified in radiation protection procedures shall be-onsite during fuel handling operations or movements of loads over storage racks containing fu-eL I Kewaunee Power Station 5.2-2 Amendment No. 2-97