ML14324A217
| ML14324A217 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 11/12/2014 |
| From: | Gatlin T D South Carolina Electric & Gas Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML14324A264 | List:
|
| References | |
| LAR-13-02396, RC-14-0179 | |
| Download: ML14324A217 (24) | |
Text
Thomas D. GatlinVice President, Nuclear Operations 803.345.4342 November 12, 2014A SCANA COMPANY RC-14-0179 U.S. Nuclear Regulatory Commission Document Control DeskWashington, D.C. 20555-0001
Subject:
VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT 1DOCKET NO. 50-395OPERATING LICENSE NO. NPF-12LICENSE AMENDMENT REQUEST LAR-13-02396 REQUEST FOR NRC APPROVAL OF CHANGES TO THE RADIATION EMERGENCY PLAN
Dear Sir or Madam:
In accordance with the provisions of Section 50.54(q) and 50.90 of Title 10 of the Code ofFederal Regulations (10 CFR), South Carolina Electric
& Gas Company, acting for itself and asagent for South Carolina Public Service Authority, hereby submits a proposed change to theVirgil C. Summer Nuclear Station's (VCSNS) Radiation Emergency Plan.VCSNS Unit 1 is proposing a change that relocates the Technical Support Center (TSC) from itscurrent location adjacent to the Main Control Room (MCR) to the basement of the NuclearOperations Building (NOB). This new location is southwest and outside of the Unit 1 Protected Area and is approximately 1900 ft from the Unit 1 Control.
Room. This change has beenevaluated under 10 CFR 50.54(q) and reductions in effectiveness have been identified; therefore, the change requires prior NRC approval.
Attachment I is the technical analysis of the proposed change. Attachment II provides the TSCchange justification and evaluation performed by VCSNS. Attachment III provides anassessment of the potential radiological consequences in the TSC. Attachment IV provides themarked-up copy of the Radiation Emergency Plan (EP-IO0 Revision 63). Attachment Vprovides the retyped copy of the Radiation Emergency Plan (EP-100 Revision XX). Attachment VI provides the new regulatory commitment.
In accordance with 10 CFR 50.91, a copy of this application, with attachments, is being providedto the designated South Carolina Official.
This letter contains one new regulatory commitment.
SCE&G requests approval of the proposed changes by June 30, 2015, with an implementation date of 90 days after issuance of amendment, to permit program changes and training.
Virgil C. Summer Station .Post Office Box 88 -Jenkinsville, SC -29065 -F (803) 941-9776 Document Control DeskLAR-1 3-02396RC-1 4-0179Page 2 of 2This proposed change has been reviewed and approved by both the VCSNS Plant SafetyReview Committee and the VCSNS Nuclear Safety Review Committee.
If you have any questions about this submittal, please contact Mr. Bruce L. Thompson at (803)931-5042.
I certify under penalty of perjury that the information contained herein is true and correct.Executed on Thomas D. GatlinBJD/TDG/ts Attachments:
VII. Analysis of Proposed ChangeI1. VCSNS TSC Change Justification/Evaluation Ill. TSC Relocation Radiation Dose Calculation (Enclosed Disk)IV. Radiation Emergency Plan (EP-100 Revision
- 63) (Mark-Up)
V. Radiation Emergency Plan (EP-100 Revision XX) (Retyped)
VI. Regulatory Commitment Pagec: Without attachments unless notedK. B. MarshS. A. ByrneJ. B. ArchieN. S. CarnsJ. H. HamiltonJ. W. WilliamsW. M. CherryV. M. McCreeS. A. Williams (w/ attachments)
K. M. SuttonS. E. Jenkins (w/ attachments)
Paulette Ledbetter NRC Resident Inspector RTS (LAR-13-02396)
File (810.10)PRSF (RC-14-0179)
Document Control DeskAttachment ILAR-13-02396 RC-14-0179 Page 1 of 6VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT IDOCKET NO. 50-395OPERATING LICENSE NO. NPF-12ATTACHMENT IAnalysis of Proposed Change1.0 DESCRIPTION Virgil C. Summer Nuclear Station, Unit 1 (VCSNS) is proposing to change the location of theTechnical Support Center (TSC) to a new location within the basement of the NuclearOperations Building (NOB). This change has been evaluated under 10 CFR 50.54(q) andreductions in effectiveness have been identified (reference Attachment II); therefore, thischange requires prior NRC approval.
2.0 PROPOSED CHANGE2.1 Relocation of the Technical Support CenterThe proposed new location for the TSC is in the basement of the NOB. This location issouthwest and outside of the Unit 1 Protected Area and is approximately 1900 ft from the Unit 1Control Room. The separation of the TSC from the Control Room (CR) will be approximately 9to 13 minutes.
This 9 to 13 minute timeframe is based on a person leaving the CR, passingthrough the Protected Area Security Control Points, then the Owner Controlled Area, andentering the NOB to access the TSC.The new facility design and layout provides a larger facility with updated audio/visual equipment to establish and maintain command and control of on-site evaluations and mitigation strategydevelopment.
Features of the new TSC include a dedicated emergency diesel generator, additional telephones, and computer resources.
The number of TSC phone lines will beincreased from 15 to 46 and the number of networked personal computers will be increased from 13 to 32. This increase will allow the ERO to access plant data, drawings, procedures, andother computer applications.
The TSC is also designed to meet the protected envelopefunctional requirements for habitability and ventilation similar to the Control Room.Attachment II provides the Licensee's justification and evaluation for the proposed change torelocate the TSC.
Document Control DeskAttachment ILAR-13-02396 RC-14-0179 Page 2 of 63.0 BACKGROUND In 2011, the NRC amended 10 CFR 50.54(q) to require the use of the license amendment process in 10 CFR 50.90, "Application for Amendment of License, Construction Permit, or EarlySite Permit,"
when applying for prior NRC approval of those changes determined to be areduction in effectiveness.
The Unit 1 Technical Support Center (TSC) is currently located within the Control Buildingadjacent to the Unit 1 Control Room. The TSC is proposed to be relocated to the NuclearOperations Building basement.
The new TSC will address the limited work area in the currentTSC and will support the eventual common TSC for a multiple unit site.4.0 TECHNICAL ANALYSIS4.1 Relocation of the Technical Support CenterThe proposed change to relocate the TSC is a reduction in effectiveness from the currentemergency plan requirements.
Table 1 provides a direct comparison between the capabilities ofthe current TSC facility and proposed new facility.
Table 1 TSC Resource Comparison Resource Current Facility Proposed FacilityTSC -14 VCS, 12 NRC withERO Positions Assigned TSC -13 VCS, 6 NRC Back-up OSC -Approximately 15VCSApproximately 7000 sq ftSquare Footage (total) Approximately 2,500 sq ft Command AreaFacilities shared with Control Full men's and women's facilities Room for men and women with showersKitchenette shared with Break Area with tables andBreak/Serving Area Control Room serving area, ice, water,refrigerator, etc.Work Stations (total) 13 49 with 3 additional conference table seating areasTelephones (PBX) 13 52Telephones (Satellite) 1 2Telephone (Dedicated Lines) 1 1 analogRadios Hand-held only 10 desk top for dedicated positions and hand-held Computers/Data Connections 13 35 with 9 in Back-up OSCProjectors (AN System) 2 5 with additional 15 AN displaycapabilities in adjacent workareasBack-up OSC None Approximately 880 sq ft with 9work stations and command tableApproximately 390 sq ft with 4NRC Area 8 x 8 cubicle work stations and conference I I_ table Document Control DeskAttachment ILAR-13-02396 RC-14-0179 Page 3 of 6The number of phones and computer work stations listed in the proposed TSC facility mayincrease or decrease in the future. However, any changes to the number of phones orcomputer work stations will ensure the communication functions between the TSC and the CR,the OSC and the EOF as well as applicable government response agencies will be maintained.
The new TSC will continue to meet the intent and guidelines of NUREG-0696, "Functional Criteria for Emergency Response Facilities" and NUREG-0737 "Clarification of TMI Action PlanRequirements" with the exception of the TSC location.
The new TSC will be located within thebasement of the NOB. This location is outside of and southwest of the Unit 1 Protected Areaand is approximately 1900 feet from the Unit I Control Room. The distance between the CRand the TSC is about a 9 to 13 minute walk. This 9 to 13 minute timeframe is based on aperson leaving the CR, passing through the Protected Area Security Control Points, then theOwner Controlled Area, and entering the NOB to access the TSC. The proposed TSC locationdoes not lend itself to face-to-face communications with the Unit 1 Control Room asrecommended by NUREG-0696, section 2.2. The location of the TSC is an alternative methodto NUREG-0696 requiring the TSC to be within two minutes of the Control Room and that therebe no major security barriers between the two facilities.
While the proposed location of the new TSC does not allow for direct face-to-face communications between the Shift Manager/Interim Emergency Director in the CR and theEmergency Director in the TSC, adequate communications lines and designated positions willensure continued and effective communication.
The site currently demonstrates theeffectiveness of the communications lines and designated positions as a substitute for face-to-face communications during emergency plan drills with the VCSNS Simulator CR and thecurrent TSC. Therefore, relocation of the TSC to the new NOB will not prevent VCS frommeeting the intent of the guidance in NUREG-0696.
The new location also provides for improved off-hours staffing capabilities since responders willnot have to process through Owner Controlled or Protected Area Security access locations toreach the TSC. The relocation of the TSC will improve activation time and the capability fortransfer of critical tasks from the Control Room. The location of the TSC will also providemanagerial and technical support to plant operations personnel via the communication linksduring emergency conditions without congesting the Control Room. The new TSC will alsohave access to the plant computer and Safety Parameter Display System (SPDS) displays.
There is not an anticipated need to traverse from the TSC to the CR therefore the Protected Area security barrier will not create any adverse impact on the function of the new TSC beinglocated outside of the Protected Area. Should the need arise, security personnel are assignedin the ERO to enhance the movement of personnel between the TSC and the Control Room.The working space is considerably larger than the existing facility and will reduce currentcrowded working conditions (reference Table 1). This change will strengthen the TSCcommand and control function by allowing the TSC ERO a larger, better-designed working area.The TSC is sized to accommodate a minimum of 40 personnel and their supporting equipment.
This includes provisions for at least 12 NRC representatives.
The larger work area facilitates additional state of the art equipment for TSC personnel to perform their ERO functions.
The TSC was constructed to meet the 2006 International Building Code (IBC). Thesuperstructure of the facility was designed for IBC site class D, design category C, Business Document Control DeskAttachment ILAR-13-02396 RC-14-0179 Page 4 of 6occupancy category I1. The TSC and NOB structure are fully equipped with sprinklers andconstructed with non-combustible construction.
The basement ceiling systems, mechanical
- ductwork, plumbing, piping, sprinkler piping, and electrical systems are seismically bracedthroughout the TSC. Access to the TSC will be controlled through two direct points ofingress/egress, on the north and south ends of the basement (central and south portions of theNOB, respectively).
These points do not open directly to the exterior of the building, but areaccessed through stairways or elevators from the upper floors. Control of personnel enteringwill be done using access card readers connected to security access control computers.
The TSC was designed to meet the protected envelope functional requirements for habitability and ventilation similar to the Control Room as identified in NUREG-0696 and NUREG-0737.
The HVAC system is designed with High Efficiency Particulate Air filters and charcoal filters witha mixed air capability from both inside and outside the facility and exterior.
The system whenplaced in emergency mode, via a designated button in the TSC command area, closes specified motorized
- dampers, disables EF-1 (rest rooms exhaust fan), and energizes FFU-1 (filtered HVAC). Once this takes place, the TSC pressurizes to a minimum of 0.125 inwc (inch of watercolumn).
An alarm panel is located within the command area of the TSC that will alertpersonnel of a change in pressurization which causes the positive pressure to fall below 0.125inwc. The preventative maintenance tasks and test procedures for the TSC filtration systemand envelope are being developed.
The preventative maintenance tasks will follow themanufactures recommendations.
The test procedures will be similar to those for the controlroom envelope.
Although these changes are reductions in effectiveness, the changes will continue to meet therequirements of 10 CFR 50.47(b) and 10 CFR 50 Appendix E. The TSC will continue tomaintain adequate facilities and equipment.
The new TSC will ensure the station's emergency response will protect the public health and safety while monitoring, evaluating, and developing mitigation strategies in response to the emergency conditions.
5.0 REGULATORY ANALYSIS5.1 Applicable Requlatory Requirements
/ Criteria10 CFR 50.47(b) and 10 CFR 50 Appendix E establish emergency planning standards thatrequire:
- 1) adequate staffing;
- 2) satisfactory performance of key functional areas and criticaltasks; and 3) timely augmentation of the response capability.
The proposed change has beenevaluated to determine whether applicable regulations and requirements continue to be met.The proposed change has also been evaluated in accordance with 10 CFR 50.54(q) and resultsin a reduction in the effectiveness of the emergency plan and therefore, prior NRC approval isrequired.
The proposed change, will continue to meet the requirements of 10 CFR 50 AppendixE and the planning standards of 10 CFR 50.47(b).
Document Control DeskAttachment ILAR-1 3-02396RC-14-0179 Page 5 of 65.2 No Significant Hazards Consideration VCSNS has evaluated whether or not a significant hazards consideration is involved with theproposed changes by focusing on the three standards set forth in 10 CFR 50.92, "Issuance ofAmendment,"
as discussed below:1. Does the proposed amendment involve a significant increase in the probability orconsequences of an accident previously evaluated?
Response:
No. The proposed change to the VCSNS emergency plan does not impact thephysical function of plant structures,
- systems, or components (SSC) or the manner in whichSSCs perform their design function.
The proposed change neither adversely affects accidentinitiators or precursors, nor alters design assumptions.
The proposed change does not alter orprevent the ability of SSCs to perform their intended function to mitigate the consequences of aninitiating event within assumed acceptance limits. No operating procedures or administrative controls that function to prevent or mitigate accidents are affected by the proposed changes.Therefore, the proposed change does not involve a significant increase in the probability orconsequences of an accident previously evaluated.
- 2. Does the proposed amendment create the possibility of a new or different kind ofaccident from any accident previously evaluated?
Response:
No. The proposed change does not involve a physical alteration of the plant (i.e., nonew or different type of equipment will be installed or removed) or a change in the method ofplant operation.
The proposed change will not introduce failure modes that could result in a newaccident, and the change does not alter assumptions made in the safety analysis.
The proposedchange to the location of the TSC is not an initiator of any accidents.
Therefore, the proposedchange does not create the possibility of a new or different kind of accident from any accidentpreviously evaluated.
- 3. Does the proposed amendment involve a significant reduction in a margin of safety?Response:
No. Margin of safety is associated with the ability of the fission product barriers (i.e.,fuel cladding, reactor coolant system pressure
- boundary, and containment structure) to limit thelevel of radiation dose to the public. The proposed change does not impact operation of theplant or its response to transients or accidents.
The change does not affect the Technical Specifications or the operating license.
The proposed change does not involve a change in themethod of plant operation, and no accident analyses will be affected by the proposed changes.Additionally, the proposed change will not relax any criteria used to establish safety limits andwill not relax any safety system settings.
The safety analysis acceptance criteria are notaffected by these changes.
The proposed change will not result in plant operation in aconfiguration outside the design basis. The proposed change does not adversely affect systemsthat respond to safely shut down the plant and to maintain the plant in a safe shutdowncondition.
The emergency plan will continue to activate an emergency response commensurate with the extent of degradation of plant safety.
Document Control DeskAttachment ILAR-13-02396 RC-14-0179 Page 6 of 6Based on the above, SCE&G concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c),
and accordingly, afinding of "no significant hazards consideration" is justified.
6.0 ENVIRONMENTAL CONSIDERATIONS The proposed change to the Radiation Emergency Plan maintains the environmental bounds ofthe current environmental assessment associated with the VCSNS Unit 1. The proposedchange will not affect plant safety and will not have an adverse effect on the probability of anaccident occurring.
The proposed change does not involve (i) a significant hazardsconsideration, (ii) a significant change in the types or significant increase in the amounts of anyeffluent that may be released
- offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.
The construction of the NOB is now complete.
The NOB was designed in accordance withState and local Uniform Building Codes. Therefore, proposed changes do not result in changesto land use or water use, or result in changes to the quality of quantity of non-radiological effluents.
No changes to the National Pollution Discharge Elimination System permit areneeded. The addition of a diesel generator was reviewed to ensure compliance with the Stateof South Carolina's air regulations and was determined to have no impacts on the air or ambientair quality.
There are no impacts to historical and cultural resources.
Therefore, no changes toor different types of non-radiological environmental impacts are expected as a result of thesechanges.In conclusion, the proposed change to the Radiation Emergency Plan will not have an adverseimpact on the environment.
7.0 PRECEDENCE
This request is similar in nature to the other requests authorized by the NRC for Clinton PowerStation [ML061920575, ML063530752, and ML070540270]
and Three Mile Island NuclearStation, Unit 1 [ML023460148].
- However, the amended rule in 2011 changed the language tospecify that licensees must use the license amendment process in 10 CFR 50.90 for changesevaluated as a potential reduction in effectiveness.
Document Control DeskAttachment IILAR-13-02396 RC-14-0179 Page 1 of 8VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT IDOCKET NO. 50-395OPERATING LICENSE NO. NPF-12ATTACHMENT IITSC LAR Change Justification/Evaluation Document Control DeskAttachment IILAR-13-02396 RC-1 4-0179Page 2 of 8VCS EP-100 (TSC) LAR Change Justification/Evaluation TITLE: EP-100, Radiation Emergency Plan, Rev xx NRC Submittal (TSC) DATE: 9/04/2014 DESCRIPTION OF PROPOSED CHANGE:The Emergency Plan is being revised to relocate the Technical Support Center (TSC) to the basement of theNuclear Operations Building.
The Changes to the Emergency Plan are being made to Annex 1 Section 4.1B. A 10 CFR 50.54 (q) evaluation was performed and recorded by VCS underVCS #:E2012-013 Revision 2.DESCRIPTION AND REVIEW OF LICENSING BASIS AFFECTED BY THE PROPOSED CHANGE:NUREG-0717, SER related to V. C. Summer Nuclear Station Unit 1, Supplements 2 and 3 require and stateVCS has a radiological emergency response plan that includes elements of NUREG-0654, Revision 1 (1979criteria),
NUREG-0696, 10 CFR 50.47, and 10 CFR 50 Appendix E and will provide adequate planning basisfor an acceptable state of emergency preparedness and meets these requirements.
EP-100 Revision 5 isthe revision in which the latest Safety Evaluation Report (SER) was issued in August,1982.
Since thisrevision numerous other revisions have been made under the 10 CFR 50.54(q) process.
This revisionmaintains the intent, purpose, and function of the emergency plan as evaluated up to the current Revision63.DESCRIBE HOW THE PROPOSED CHANGE COMPLIES WITH RELEVANT EMERGENCY PREPAREDNESS REGULATION(S)
AND PREVIOUS COMMITMENT(S)
MADE TO THE NRC:NUREG-0654, 10 CFR 50.47, and 10 CFR 50 Appendix E provide regulatory requirements and guidance fora radiological emergency plan content.
This revision does affect how the regulatory or commitment requirements will be met. Changes affecting the requirements of 10 CFR 50.47 and 10 CFR 50 Appendix Eare evaluated in this evaluation.
This revision also changes the means and methods in which NUREG-0696 guidance will be met due to building a new TSC and relocating the facility.
The revision also affects theSecurity and Emergency Plan interfaces in accordance with 10 CFR 73.58, which was evaluated under siteprocedure SAP-0163 by site Security personnel and there is no adverse impact on the Security Plan orinterface.
More specifically 10 CFR 50.47 (b) (8) requires adequate emergency facilities and equipment to support theemergency response are provide and maintained.
The relocation of the TSC is evaluated in more detail inEnclosure A of this document.
This evaluation will provide the justification as to how the relocation of theTSC will continue to meet the requirements of these regulations.
DESCRIPTION OF IMPACT OF THE PROPOSED CHANGE ON THE EFFECTIVENESS OF EMERGENCY PLAN FUNCTIONS:
Enclosure A of this evaluation provides the detailed evaluation and justification of the changes.
Thesechanges were identified in the 10 CFR 50.54 (q) evaluation as a reduction in effectiveness and require priorapproval by the NRC.EVALUATION CONCLUSION:
Answer the following questions about the proposed change.1. Does the proposed change comply with the requirements of 10 CFR 50.47(b) and 10 0 YES El NOCFR 50 Appendix E?2. Does the proposed change maintain the effectiveness of the emergency plan (i.e., no E YES E NOreduction in effectiveness)?
Document Control DeskAttachment IILAR-13-02396 RC-14-0179 Page 3 of 8Enclosure A, Technical Support Center Relocation Justification/Evaluation Justification:
Function:
The Unit 1 Technical Support Center (TSC) is currently located within theControl Building adjacent to the Unit 1 Control Room. The TSC is proposed to be relocated to theNuclear Office Building basement.
The new TSC will address the limited work area in the current TSCand will support the eventual common TSC for a multiple unit site.The new TSC facility is designed to meet the intent and requirements of NUREG-0696 "Functional Criteria for Emergency Response Facilities" and NUREG-0737 "Clarification of TMI [Three Mile Island]Action Plan Requirements".
This location departs from the guidance in NUREG-0696 in three areas: 1)that the TSC be located near the Control Room, 2) that the walking time from the TSC to the ControlRoom not exceed 2 minutes, and 3) that there be no major security barriers between the TSC and theControl Room. However, with improved electronic communication capabilities and technologies, face toface interactions between the TSC and Control Room personnel are no longer necessary to meet theintent of NUREG-0696 guidance.
VCS drills are currently conducted in a manner that does not afford theface to face interactions, due to the Simulator being in the training
- building, outside the Protected Area.Therefore, relocation of the TSC to the new NOB will not prevent VCS from meeting the intent of theguidance in NUREG-0696.
When activated, the TSC functions include:* Support for the affected Control Room's emergency response efforts" Continued evaluation of event classification
" Assessment of the plant status and potential offsite impact* Coordination of emergency response actions within the Protected Area (PA)" Communication with the NRC via ENS" Activation of the Emergency Response Data System (ERDS) or ensuring that it is activated Location:
VC Summer (VCS) has built a new Nuclear Operations Building (NOB) and within its basementis a proposed new Technical Support Center (TSC). The NOB and proposed TSC will be located outsideof and southwest of the Unit 1 Protected Area. This location is approximately 1900 ft. from the Unit 1Control Room. The separation of the TSC from the Control Room will be approximately 9 to 13 minutes(under normal walking conditions) and includes processing time through Owner Controlled Area andProtected Area Security Control Points. The basement of the NOB is dedicated only for the TSC. TheTSC access is controlled via security card access readers or key locked doors. Designation of the accessauthorization levels is the responsibility of VCS Emergency Preparedness and is controlled by Corporate Security via security access request and approval process.During a radiological emergency requiring an emergency declaration, Security procedures and actionswill not inhibit access through the Owner Controlled and Protected Area access systems.
Thus thesesystems have a negligible impact on travelling from the TSC to the Control Room or other portions of theplant. In the event of a hostile action, plant procedures provide guidance for the Emergency ResponseOrganization (ERO) to activate utilizing alternate facilities, outside of potential hostile action areas, andprovide procedure guidance for moving personnel under protective measures.
The relocation of the TSCwill not impact the use of the alternate facilities.
The VCS Emergency Plan describes extensive communications capabilities between the TSC and theUnit 1 Control Room, OSC, and EOF. These communications capabilities provide a variety of methods toensure reliable communications and compensate for the TSC being located outside of the Protected Area. NUREG-0800 Section 13.3.111, includes a statement that advanced communication capabilities maybe used to satisfy the 2-minute travel time. The communication capabilities between the Control Roomand the new TSC are a suitable alternative to the two minute travel time. Management interaction and Document Control DeskAttachment IILAR-1 3-02396RC-1 4-0179Page 4 of 8technical information exchange will be accomplished using plant computer and communication (telephone, radio, etc.) systems that provide means to directly contact the Control Room. The capabilities to review and evaluate technical data, such as plant parameter display information, are provided in theTSC from real-time systems which receive their inputs from the same sources as the Control Room, butare communicated on a different network.
Access to procedural information and plant reference materialwill continue to be available in the new TSC. The use of technology to access and evaluate plantparameters significantly reduces the need for face-to-face interactions described in NUREG-0696.
In the event that TSC personnel are to travel to the Control Room during a radiological release or if arelease is imminent, the TSC has storage capabilities for maintaining protective clothing and surveyinstruments that will be needed to ensure dose received during travel is as low as reasonably achievable.
The location of the TSC also affords the opportunity to use multiple routes to reach the Control Room tominimize exposure to a potential plume or release path.Staffing and Training:
The proposed TSC is designed to support an emergency for VCS Unit 1 and in thefuture Units 2 and 3 or any combination thereof.
The Unit 1 TSC requires hosting equipment and workspace to support approximately thirteen ERO positions.
The proposed TSC will host approximately fourteen ERO positions, including designated work space for the NRC Residents.
This organization willhave access to and can evaluate emergency conditions for Unit 1 using plant computer systems toprovide operational parameters and meteorological data. The organization structure can maintaincommunications with the Control Room, the Operational Support Center, and the Emergency Operations Facility.
This change will also strengthen the TSC command and control function by allowing the TSCERO a larger, better designed working area.The Nuclear Operations Building upper floors house Engineering, Site Management, and other plantorganizations and personnel assigned to the ERO to augment Shift Staffing in an emergency.
This closeproximity will facilitate timely activation of the TSC during normal work hours. This location also providesfor improved off-hours staffing capabilities since responders will not have to process through OwnerControlled and Protected Area security access systems to reach the TSC. The relocation of the TSC willmake activation timelier and improve the capability for transfer of critical tasks from the Control Room.ERO Training will be maintained as currently described in the emergency plan and implementing procedures.
Personnel training specific to their ERO assignments will be modified to incorporate changesbased the relocation of the TSC and the new work station arrangements.
Emergency drill training iscurrently conducted using the TSC in the Unit 1 Control Building (adjacent to the actual Control Room)and the simulator Control Room located in the Nuclear Learning Center, without the ability to have face toface communication between TSC and Control Room personnel.
These drills have successfully demonstrated the ability to implement the Emergency Plan with a physically separated Control Room andTSC.Size: The new TSC command area and adjacent work areas total approximately 7,000 square feet ascompared to the current TSC space of approximately 2,500 square feet. This provides more thanadequate spacing and exceeds 75 square foot /person required in NUREG-0696.
The TSC will bedesigned around a central command center with partitioned work spaces on its perimeter for designated support groups. Each work space has full viewing of the command area through glass store frontpartition walls. The facility (basement) also includes restrooms with shower facilities, a break room(refrigeration, ice and beverage, and serving areas), storage areas, and communications/network, audio/visual equipment, copier/printer, electrical and mechanical rooms supporting only the new TSCarea. An established designated boundary will ensure the TSC portions of the basement are protected bythe HVAC/Recirculation-Filtration envelop.The new facility will provide larger individual work spaces and designated discipline work areas andconference areas as compared to the existing TSC. The command area will increase from thirteen workstations to forty-nine work stations.
The engineering area will expand from two shared work spaces toeleven work spaces. The facility also includes two separate work areas that each support three workstations.
The TSC will also include a designated NRC support area which expands from one work space Document Control DeskAttachment IILAR-1 3-02396RC-1 4-0179Page 5 of 8to four work spaces and a conference area directly adjacent to the command area and separated by aglass partition wall. The TSC will include a back-up Operational Support Center (OSC) in an adjacentwork area with nine work stations and a large command center table. This area is separated from thecommand area by glass partition walls. If not needed as a back-up OSC; this space can be utilized bythe TSC staff in the response to an emergency.
With larger work areas, additional technology (computers and telephones) has been provided to the TSCpersonnel.
The new TSC will allow personnel to access plant data, drawings, procedures, and othercomputer applications more timely and effectively from individual work stations.
Technology in the newTSC will also include multiple overhead projection
- systems, large screen displays, teleconferencing, realtime system monitoring through plant computer
- networks, and radio, PBX, and satellite phonecommunication systems.Structure:
The TSC will be located in the basement of the Nuclear Operations
- Building, below two upperstructural floors which are designed and constructed to the 2006 International Building Code. Access tothe TSC will be controlled through two direct points of ingress/egress, on the north and south ends of thebasement (central and south portions of the NOB, respectively).
These points do not open directly to theexterior of the building, but are accessed through stairways or elevators from the upper floors. Thebasement of the NOB is dedicated only for the TSC. The TSC access is controlled via corporate securitycard access readers or key locked doors. Designation of the access authorization levels is theresponsibility of VCS Emergency Preparedness and is controlled by Corporate Security via securityaccess request and approval process.
The NOB is located within the Exclusion Area of the site which ispatrolled and controlled by onsite security forces.The basement of the NOB, which is where the TSC will be housed, is constructed of 10-12" thick concreteretaining walls and is located 16 feet below finished exterior grade. The floor structure of the NOB aboveforms a cap above the space. This cap is constructed of a composite beam and concrete slabconstruction.
The TSC and NOB structure are constructed with non-combustible material and areprotected by a sprinkler system. The superstructure of the facility is designed to International BusinessCode (IBC) site class D, design category C, Business occupancy category I1. The basement ceilingsystems, mechanical
- ductwork, plumbing piping, sprinkler piping, and electrical systems are seismically braced throughout the TSC.Habitability:
The TSC is designed to meet the protected envelope functional requirements for habitability and ventilation similar to the Control Room as identified in NUREG-0696 and Section Il.B.2 of NUREG-0737. The HVAC system is designed with High Efficiency Particulate Air filters and charcoal filters with amixed air capability from both inside and outside the facility.
The system when placed in emergency mode, via a designated button in the TSC command area, closes specified motorized
- dampers, disablesEF-1 (rest rooms exhaust fan), and energizes FFU-1 (filtered HVAC). Once this takes place the TSCpressurizes to a minimum of 0.125 inches water column (inwc). An alarm panel is located within thecommand area of the TSC that will alert personnel of a change in pressurization which causes thepositive pressure to fall below 0.125 inwc.The HVAC design includes the following:
The mechanical ventilation for the TSC area is designed to provide 4000 cubic feet per minute (cfm) ofoutside air prior to isolation.
When the system is placed in emergency mode, a total of 4000 cfm will befiltered with charcoal and HEPA filtration.
While in emergency mode, 3200 cfm of the 4000 cfm will beoutside air and the remaining 800 cfm will be recirculated from the TSC area while maintaining a 0.125inch positive pressure.
During the normal mode of operation, the system provides conditioned airflow to the terminal boxesserving the spaces. As the space temperatures are satisfied, the dampers on the boxes start to closecausing the supply fan to slow down. The speed of the supply fan will vary depending on the buildingload. The return air damper modulates to maintain a positive pressure differential between the TSC Document Control DeskAttachment IILAR-13-02396 RC-14-0179 Page 6 of 8boundary area and the outdoors.
A pressure monitor located in the TSC to provides positive pressureverification.
The TSC area is placed in the emergency mode from a push button located in the TSC. When thesystem is in emergency mode, the outside supply and return dampers reposition and direct flow to thefiltered flow unit (FFU). The FFU has Minimum Efficiency Rating Value (MERV) 8 pre-filters, MERV 15charcoal
- filters, and MERV 16 final filters and works with the normal air handling unit to provide filtered airand maintain a positive pressure differential between the TSC boundary area and the outdoors.
- 1. TSC ventilation air inlet and recirculation flow rates -The system design provides 3200 cfm ofoutside air make-up (unfiltered) to the TSC prior to isolation, after isolation 3200 cfm (filtered).
Anadditional 800 cfm of air is recirculated through the charcoal cleanup unit.2. HEPA filter and charcoal absorber fission product removal efficiencies
-The system provides99% removal efficiency for particulates and 90% decontamination efficiency for radioiodine.
- 3. TSC unfiltered air in-leakage rate -The in-leakage assumed for the TSC dose calculation is 500cfm of unfiltered air after isolation.
- 4. Atmospheric dispersion factors (X/Q values) at TSC air intake -The X/Q values at the TSC airintake are as follows, with the release assumed at ground level from the location of the plant vent.These values which bound the containment shell ground level release are calculated usingARCON96 based on two years of meteorological data:0-2 hr 2.33E-05 sec/m32 -8 hr 1.84E-05 sec/m38 -24 hr 7.65E-06 sec/m324 -96 hr 6.OOE-06 sec/m396 -720 hr 4.58E-06 sec/m35. TSC occupancy factors -The standard Control Room occupancy factors from Section 4.2.6 ofRegulatory Guide 1.183, July 2000, are assumed for the TSC:0-24 hr 1.0 (100%)24 -96 hr 0.6 (60%)96 -720 hr 0.4(40%)6. TSC free air volume -The TSC design is approximately 72' by 130', with an additional 14' by 40'area provided as a potential eating area. The floor area does not include those vestibule areasthat function as air locks between stairways and the TSC, but does include areas that contain theventilation system fans and filter plenums.
The floor to ceiling height is 14.5'. These dimensions provide a volume of 143,840 ft3 for the dose evaluation of the facility.
The TSC free air volumewill be no greater than 143,840 ft3.7. Occupant breathing rate -The breathing rate of 3.5E-4 m3/sec for the TSC occupant is assumedfor the duration of the accident.
This rate is consistent with that for the control room operator inSection 4.2.6 of Regulatory Guide 1.183, July 2000.8. Description of the ventilation design -The ventilation design for the TSC is modeled after Figure 1of Regulatory Guide 1.52, Revision 3, June 2001, with minor deviations.
Neither the moistureseparators nor the heater are expected to be required in the charcoal unit. The ventilation equipment will be located within the TSC ventilation
- envelop, within a mechanical room.During normal operation the system functions as a normal ventilation system providing temperature
- control, filtration, and some amount of outside air make-up.
During emergency recirculation conditions acharcoal absorber unit is placed in service.
This unit is intended to provide filtration of part of the air beingrecirculated in the TSC as well as the outside air make-up for the TSC. During the emergency Document Control DeskAttachment IILAR-13-02396 RC-14-0179 Page 7 of 8recirculation mode of operation the system maintains a 1/8 iwc positive pressure in the TSC relative tooutside, by admitting 3200 cfm of outside air. This flow of 3200 cfm provides enough ventilation (filtered fresh air) for at least 100 people. The charcoal absorber unit filters an additional 800 cfm of air that isrecirculated from the TSC. There is also an unfiltered recirculation rate of 15,000 cfm, but this has nobearing on the radiological analysis.
The HVAC system is not designed as Seismic Category I and is not provided with redundant fans, filters,or power supplies, as allowed by the NUREG-0696 requirements for the TSC. Each TSC entrance isprovided with a weather sealed doorway between stairways and the TSC Command Area.Exposure to direct radiation from a radiological release is negligible due to the TSC being located in thebasement and beneath the two upper floors of the NOB. Based on current Unit 1 TSC dose calculations and taking the conservative approach that the new TSC will be further away from the plant and in thebasement of the Nuclear Operations
- Building, the expected dose rates and TEDE accumulated dose isexpected to be less than 5 Rem.Radiological monitoring will be provided using a portable Beta Continuous Air Monitor (CAM). Themonitor will be mounted on a portable cart and rolled into the hallway immediately adjacent to the TSCCommand Area and within the HVAC envelop.
The monitor will meet the follow specifications:
Microprocessor-based central readout device, mated to a detection head with real timegamma background subtraction using two detectors 12 in. diameter sealed proportional Window: 2 to 3 mg/cm2 micaRadial Sampling Head: 8.5% 60Co, 17% 90Sr/90Y (nominal)
Inline Sampling Head: 6.4% 85Kr, 4.4% 133Xe (nominal)
Noble Gas Sampling Head: 5.75% 60Co, 12% 90Sr/90Y (nominal)
Display Unit: 8.5 to 113 L/min., 0.5 to 6.8 cfh (0.3 to 4.0 cfm)Pump: 56 L/min. (2.0 cfm) nominal at STP with clean filterTwo rows x 20 characters high visibility vacuum fluorescent, percentage of Alarm 40-element LED bar graphFront panel lights display READY and MALFUNCTION conditions, red alarm strobe lightvisual warning, and sonalert audible warningCommunications and Data Systems:
The TSC will have voice, data, and radio communication services.
These services will be distributed from a dedicated communication room allowing independence from thedistributed network services in other parts of the building.
Additionally, the TSC will have radio and fiberoptic capabilities that can communicate with the Control Room, OSC, EOF, and offsite emergency
- agencies, if needed.Network Transport (feeds to the building):
Two network transport feeds come to the TSC from the AccessAuthorization Portal currently, which is redundantly fed from the corporate network.
The system will beupgraded in the future providing two 10 gig feeds, one from Fiber Hut (FH) 2 and the other from FH5.FH2 and FH5 will have diverse 10 gig feeds, one from 1401 Main St. Columbia, SC and the other fromthe 24x7 data center in West Columbia, SC.Dual Independent Distribution switches:
The 2 transport feeds are connected to two distribution
- switches, DistSNOBA and DistSNOBB.
The distribution switches have dual power supplies.
One power supply isconnected to an emergency power source and the 2nd power supply is connected to the building UPSsystem; the switch can operate on one power supply. Each power supply is running at half capacity andconfigured to take over should one of them fail or lose power.
Document Control DeskAttachment IILAR-13-02396 RC-14-0179 Page 8 of 8Access Switches:
There are two access switches in the TSC communication room, SW1SNOBB andSW2SNOBB.
All PCs, printers, building security
- systems, AV systems, building management
- systems, IPPhones, and IP radios are connected to the access switches.
Each access switch has an uplink to thedistribution switch, one to DistSNOBA and the other to DistSNOBB.
Each access switch has two supervisor modules.
These modules contain the switch configuration and asingle 10 gig uplink to the distribution switch. One is active and the second one is in standby mode.Should the active one fail or have a problem, the second supervisor module takes over the management and operation of the switch.Each access switch has dual power supplies; one power supply can run the switch. Both power suppliesare powered up, running at half capacity and configured to take over should one fail or lose power. Onepower supply is connected to an emergency power source and the second power supply is connected thebuilding UPS system.With the redundancy of the TSC communication
- services, there is no one point of failure that will interrupt services.
Instrumentation, Data System Equipment, and Power Supplies:
The HVAC system is controlled by the Building Management system which provides system diagnosis and alarms to site facilities maintenance personnel.
The facility has normal and emergency 480 volt power distribution equipment on the ground floorelevation which feed an automatic transfer switch (ATS) that supplies power to the building emergency power distribution panels. The main emergency power distribution panel feeds a 480 volt panel in thebasement (TSC) electrical room that feeds additional panels that supply power for lighting, HVACequipment, the uninterruptible power system (UPS), and other 480 volt loads. Step down transformers are located in the basement to supply panels that feed receptacles and other 120 volt and 208 volt loads.In the event of a loss of normal power the ATS will transfer to the emergency diesel generator.
Thegenerator feeding the emergency power system is a 550 KW diesel engine generator with adequatecapacity to supply emergency power loads in the TSC as well as the other emergency loads in thebuilding.
Lighting and HVAC systems in the TSC are on emergency power. 120 volt receptacles are fedfrom emergency power panels and receptacles for critical equipment and computers are fed from theUPS system. The TSC emergency generator powers TSC loads and limited loads within the remaining NOB to allow access safely into the TSC. These loads include, but are not limited to, emergency
- lighting, elevator power, and security systems.
Document Control DeskAttachment IIILAR-1 3-02396RC-14-0179 VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT IDOCKET NO. 50-395OPERATING LICENSE NO. NPF-12ATTACHMENT IIITSC Relocation Radiation Dose Calculation Enclosed on Disk Document Control DeskAttachment IVLAR-13-02396 RC-14-0179 Page 1 of 3VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT 1DOCKET NO. 50-395OPERATING LICENSE NO. NPF-12ATTACHMENT IVProposed Radiation Emergency Plan (EP-100 Revision
- 63) (Mark-Up)
SOUTH CAROLINA ELECTRIC
& GAS COMPANYVIRGIL C. SUMMER NUCLEAR STATIONNUCLEAR OPERATIONS NUCLEAR OPERATIONS COPY NO.RADIATION EMERGENCY PLANEP-100REVISION 63SAFETY RELATED Annex 1: Unit 1V. C. Summer Nuclear StationSection 4: Emergency Facilities and Equipment 4.1 Unit-Specific Emergency Facilities A. Control RoomThe Control Room, located in the Control Building is designed to be habitable underaccident conditions and shall serve as the onsite Emergency Control Center. Emergency
- lighting, power, air filtration, ventilation system and shielded walls enables the operators toremain in the Control Room to ensure that the reactor will remain in a safe condition.
Inaddition, the operators shall be able to evaluate situational conditions and relay pertinent information and data to the appropriate onsite and offsite agencies and organizations during all emergencies.
To ensure that shift personnel and other personnel assembled atthe location can remain self-sufficient, emergency equipment and supplies shall be storedin, or near, the Control Room. The exact location and the type and quantity of emergency equipment and supplies available are specified in EPP-103, Emergency Equipment Checklist.
B. Technical Support Center (TSC)The TSC, located in the Gentra--basement of the Nuclear Operations Building is designedto be habitable under accident conditions and shall serve as the onsite Emergency ControlCenter after relieving the Control Room of command and control.
Emergency
- lighting, power, air filtration, ventilation system, and below earthen gqradeshielded walls enable theresponders to remain in the TSC. In addition, the responders shall be able to evaluatesituational conditions and relay pertinent information and data to the appropriate onsiteand offsite agencies and organizations during all emergencies.
This facility is locatedieidle-outside the Unit 1 Protected Area approximately 1900 ft from the Control Room andprovides the ability to respond and activate the facility in a timely fashion.C. Operational Support Center (OSC)The OSC is located on the first floor in the Auxiliary Service Building within the Protected Area and is separate from the Control Room. The OSC is the location from which survey,operations, and repair teams are dispatched into areas of the plant. It is the staging areafor individuals who may be assigned to first aid, search, survey, rescue, repair, andcorrective action teams.The OSC Supervisor is responsible for managing the activities in the OSC including:
- Ongoing accountability of anyone dispatched from the OSC. The Control RoomSupervisor or the Security Shift Supervisor track individuals who are assigned to theControl Room or the Security Force respectively.
- Radiological exposure control for the individuals within the OSC" Mobilizing individuals on the emergency roster needed to fill the positions in the OSCand other support personnel such as materials and warehouse personnel The OSC is activated with a minimum staff within about 60 minutes after the declaration ofan Alert, SAE, or GE.PAGE 147 OF 191EP-100 Rev 63 Document Control DeskAttachment VLAR-13-02396 RC-14-0179 Page 1 of 3VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT IDOCKET NO. 50-395OPERATING LICENSE NO. NPF-12ATTACHMENT VProposed Radiation Emergency Plan (EP-100 Revision XX) (Retyped)
SOUTH CAROLINA ELECTRIC
& GAS COMPANYVIRGIL C. SUMMER NUCLEAR STATIONNUCLEAR OPERATIONS NUCLEAR OPERATIONS COPY NO.RADIATION EMERGENCY PLANEP-100REVISION XXSAFETY RELATED Annex 1: Unit IV. C. Summer Nuclear StationSection 4: Emergency Facilities and Equipment 4.1 Unit-Specific Emergency Facilities A. Control RoomThe Control Room, located in the Control Building is designed to be habitable underaccident conditions and shall serve as the onsite Emergency Control Center. Emergency
- lighting, power, air filtration, ventilation system and shielded walls enables the operators toremain in the Control Room to ensure that the reactor will remain in a safe condition.
Inaddition, the operators shall be able to evaluate situational conditions and relay pertinent information and data to the appropriate onsite and offsite agencies and organizations during all emergencies.
To ensure that shift personnel and other personnel assembled atthe location can remain self-sufficient, emergency equipment and supplies shall be storedin, or near, the Control Room. The exact location and the type and quantity of emergency equipment and supplies available are specified in EPP-103, Emergency Equipment Checklist.
B. Technical Support Center (TSC)*The TSC, located in the basement of the Nuclear Operations Building is designed to behabitable under accident conditions and shall serve as the onsite Emergency ControlCenter after relieving the Control Room of command and control.
Emergency
- lighting, power, air filtration, ventilation system, and below earthen grade walls enable theresponders to remain in the TSC. In addition, the responders shall be able to evaluatesituational conditions and relay pertinent information and data to the appropriate onsiteand offsite agencies and organizations during all emergencies.
This facility is locatedoutside the Unit I Protected Area approximately 1900 ft from the Control Room andprovides the ability to respond and activate the facility in a timely fashion.C. Operational Support Center (OSC)The OSC is located on the first floor in the Auxiliary Service Building within the Protected Area and is separate from the Control Room. The OSC is the location from which survey,operations, and repair teams are dispatched into areas of the plant. It is the staging areafor individuals who may be assigned to first aid, search, survey, rescue, repair, andcorrective action teams.The OSC Supervisor is responsible for managing the activities in the OSC including:
- Ongoing accountability of anyone dispatched from the OSC. The Control RoomSupervisor or the Security Shift Supervisor track individuals who are assigned to theControl Room or the Security Force respectively.
- Radiological exposure control for the individuals within the OSC" Mobilizing individuals on the emergency roster needed to fill the positions in the OSCand other support personnel such as materials and warehouse personnel The OSC is activated with a minimum staff within about 60 minutes after the declaration ofan Alert, SAE, or GE.PAGE 128 OF 191EP-100 RevXX Document Control DeskAttachment VILAR-13-02396 RC-14-0179 Page 1 of 1VIRGIL C. SUMMER NUCLEAR STATION (VCSNS)ATTACHMENT VIREGULATORY COMMITMENT The following table identifies those actions committed to by SCE&G, Virgil C. Summer NuclearStation in this document.
Any other statements in this submittal are provided for information purposes and are not considered to be commitments.
Please direct questions regarding thesecommitments to Mr. Bruce L. Thompson,
- Manager, Nuclear Licensing, (803) 931-5042.
COMMITMENT Due Date/Event Develop preventative maintenance tasks and test March 19, 2015procedures for the TSC filtration system andenvelope.