ML20154M428
| ML20154M428 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 09/20/1988 |
| From: | Hayes J Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| GL-88-12, NUDOCS 8809280292 | |
| Download: ML20154M428 (21) | |
Text
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SEP 2 01988 i Docket No. 50 395 5
! LICENSEE: South Carolina Electric & Gas Company FACILITY: V. C. Summer Nuclear Station j
SUBJECT:
SUKHARY OF MEETING WITH SOUTH CAROLINA ELECTRIC & GAS COMPANY General i
On August 17, 1988, the NRC staff consisting of representatives of the Office of Nuclear Reactor Regulation, met with the South Carolina Electric & Gas i Company (SCE&G) to discuss the removal of the fire protection technical specifications for the V. C. Sumer Nuclear Station and the recent issuance of Generic Letter 8812 "Reinoval of Fire Protection Requirements from Technical l Specifications." The meeting was held at the NRC offices in Rockville,
- Naryland. A list of those persons who attended the meeting is included as Enclosure 1.
j Discussion 1
SCE&G's submittals of March 31, 1987 and June 20, 1988 were discussed in i detail. Additional review of these submittals will be performed by SCE&G to
- 2nsure that they conform to Generic Letter 88-12. Schedule will be discussed
- later due to the beginning of the refueling outage on Septer..ber 16, 1988.
Enclosure 2 consists of the handouts which were discussed during the meeting.
l s John J. Hayes, Jr. , Project Manager
- Project Directorate II-1 d
Division of Reactor Projects I/II
Enclosures:
j As stated i cc w/enclosurcs:
See next page g S\
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NAME :q..JJ,tj ch v am : : : : :
DATE : 9////88 , 9/w/88 : : : : :
I Off!CIAL RECORD COPY G309280292 GSO920 fDR ADOCK 0500 g 5
L e Mr. O. S. Bradham South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station CC:
Mr. William A. Williams, Jr.
Technical Assistant - Nuclear Operations 4 Santee Cooper P.O. Box 764 (Mail Code 153)
Columbia, South Carolina 29218 J. B. Knotts, Jr. , Esq.
Bishop. Cook, Purcell and Reynolds 1400 L Street, N.W.
Washington, D. C. 20005-3502 Resident inspector / Summer hPS c/o U.S. Nuclear Reculatory Commission Route 1, Box 64 Jenkinsville South Carolina 29065 Regional Administrator, Region II U.S. Nuclear Regulatory Commission.
101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323
- l. Chairman, Fairfield County Council
- P.O. Box 293 Winnsboro, South Carolina 29180 Attorney General
! Box 11549 Columbia, South Carolina 29211 Mr. H'eyward G. Sheely. Chief
, Bureau of Radiological Health
- South Carolina Department of Health
! and Environmental Control l 2600 Bull Street l
Columbia, South Carolina 29201 l South Carolina Electric & Gas Company i Mr. A. R. Koon, Jr. , Manager Nuclear Licensing Virgil C. Summer Nuclear Station
- P. O. Box E6 j Jenkinsv111e, South Carolina 29065 i
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i EhCLOSURE 1 1
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ATTENDANCE i a
August 17, 1988 Meeting i
SCE8G NRC Observers
- l H. Donntily D. Kubicki L. Trout Jr. r T. Keckeisen E. Reeves ( Alabama Power Co.) l i
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.. t EhCLOSURE 1 i 4 :
ATTENDANCE !
j August 17, 1988 Meeting ,
4 4 SCE8G NRC Observers i l
, H. Donnelly O. Kubicki L. Trout. Jr. !
T. Keckeisen E. Reeves ( Alabama Power Co.)
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ENCLOSURE 2 V
W ThWN
/ g-IfRR @ESTIONS RELATED TO REMOVAL OF FIRE PROTECTION RE@IREMENTS FROM TECHNICAL SPECIFICATIONS j.fM-h5 Requirement for Section 6.2.2.c Site Fire Brigade Requirementss should remain within the Technical Specifications. d 7
A ThisdeterminationwillbemadeafterdiscussionwithNRR.!
jS Does a requirement exist in Technical Specifications to estabitsh written procedures fcr the Fire Protection Program?
A Yes Section 6.8 requires this. (See page 6-13 of the Technical Specifications.)
Present submittal uses words "equivalent level of limiting conditions...." Initial programs should use "identical" Technical Specifications requirements.
A Initial program does use identical requirement. (Seeletterof clarification.) M ( L.gf'-o/2 //
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M/S Does the FSAR/FPER address a comitment to the NFPA codes and are these codes met?
A Section 9.5.1 addresses the comitment. Codes are utilized as guides as described wit';in the program.
[S The Fire Protection Program should be included in Section 9.3 of the FSAR or referenced in this section.
A The Fire Protection Program is included by reference. (Seepage 9.5-1.)
/Q/S The related Fire Protection letters should be referer. cad with Jhe FSAR/FPER. Especially letters dated April 23, 1986 and May 2,6, 1985. SER's should reflect complete program. 4 A The two letters are referenced in the FPER. (See page.3.1-5.) The most recent SER's address the re-evaluated Appendix R program and were incorporated into the FPER via Revision Notice #730 (attached).
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j0NINISTRATIVECONTROLS - - - .
- d. Critical operatio. of the unit shall not be resumed until authorized I
by the Commission.
6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained j covering the activities refsrunced below:
- a. The doplicable procedures recommended in Appendix "A" of Regulatory Guide 1.33 Revision 2, February 1978.
- b. Refueling operations,
- c. Surveillance and test activities of safety related equipment.
- d. Security Plan,
- e. Emergency Plan,
- h. OFFCITE DOSE CALCULATION MANUAL.
- 1. Effluent and enviionmental monitoring program using the guidance in Regulatory Guide 4.15, Revision 1, February 1979.-
6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed prior to implementation as set forth in 6.5 above.
6.8.4 The following programs shall be established, implemented, and maintained:
- a. Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systees outside cont?inment that could contain highly radioactive fluids during a i
serious transient or accident to as low as practical levels. The systems include the cheetcal and volume control, letdown, safety injection, residual heat removal, nuclear sampling, liquid radweste handling, gas radwaste handling and react?r building spray system.
l The program shall include the following:
(1) Preventive maintenance and periodic visual inspection requirements, and (ii) Integrated leak test requirements foa each system at refueling cycle intervals or less,
- b. In-Plant Radiation Monitoring A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This progras shall incluod the following:
(i) Trakningofpersonnel, (ii) Procedures for monitoring, and (iii) Provisions for maintenance of sampling and analysis equipment, e
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SUHHER - UNIT 1 6-13 l
10CFR50036a August 29, 1988 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Virgil C. Sumer Nuclear Station Occket No. 50/395 Operating License NO. NPF-12 Fire Protection Technical Specification Amendment Request Gentlemen:
As described in our March 31, 1987 and December 21, 1987 letters, South Carolina Electric & Gas Co.npany (SCE&G) has been evaluating the concept of amending the FSAR, by incorporating our Fire Protection Evaluation Report (FFER) into the FSAR Chapter 9 by reference and removing the fire protection elements from the Virgil C. Sumer Technical Specifications. This will transfer the fire protection program commitments, reporting requirements and amendment from the jurisdiction of 10CFR50.73 and 10CFR50.90 to 10CFR50.71(e). The Summer Fire Protection Program will be completely described and controlled through the FSAR/FPER and Station Administrative procedures rather than through the combination of FSAR/FPER and Technical Specifications. This will be consistent with the recommendations contained in Generic Letter 86-10 ./ c C. I! -l 1 The fire protection program in place at the Virgil C. Summer Nuclear Station meets the requirements of existing Technical Specifications. With relatively straightfcrward changes, the fire protection program can he incorporated into the FSAR/FPER as recomended by the Generic Letter. Based on discussions with the staff on August 17, 1988, the fire prot tion associated sections will be removed from the Technical Specifications e existing Surveillance Test Procedures will be enained by converting them o Preventative / Fire Tes:
Procedures. The limitirg conditions and remedial action portions of these sections will be re-established by expanding an existing Station Administrative procedure. The same level of limiting conditions, and actions to be taken will be established within this procedure and other plant procedures to provide a level of protection as described in the existing Technical Specifications.
If your have any question, please advise.
Very truly yours,
- 3. A. Nauman c: See page 2
Document Contrcl Desk l August 29, 1988
, Page 2 HID/ DAN:bgh Attachments c: D. A. Nauman J. G. Connelly, Jr. ,
E. C. Roberts W. A. Williams, Jr. [
J. N. Grace -
1 J. J. Hayes, Jr.
General Managers
- o. C. A. Price /R. M. Campbell, Jr. :
- R. B. Clary j K. E. Nodland !
4 J. C. Snelsv> l j G. O. Percival !
, R. L. Prevatte l J. B. Knotts, Jr.
! H. G. Shealy :
NSRC .
! NPCF !
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s 9.5 OTHER AURILIARY SYSTEMS 9.5.1 FIRE PROTgCTION SYSTEN 9.5.1.1 Des! u Bases The fire protection system is designed to provide adequate fire protection for each hazard. It provides prompt fire detection, alarm and eatinguishment. The fire protection system is designed to supplement the other fire protection safeguards incorporated into the plant design, including a low combustible fire loading and adequate separation of fire areas. Included in the total fire protection system are a fire protection water supply and distribution systes, a fire detection and alarm system and gaseous eatinguishing systems, as well as fixed water spray and automatic
, sprinkler systems.
The fire protection systems are also addressed in the Fire Protection Evaluation Report (FPER), which is considered a part of this FSAR. The FPER has as its objective the evaluation of the potential effects of a fire in any location in the plant and to demonstrate that a fire would not ado esely affect safe shutdown and would not result in an uncontrolled releasu of l radioactivity.
The fire protection system has been designed to satisfy the interest and i concerns expressed in the guidelines given in the National Fire Protection l Association (NFPA) Standards 1973, the requirements of the American Nuclear Insurers (ANI) 1976, and the Factory Mutual (FM) Loss Prevention Guidelines j 1973. In addition, it complies with occupational Safety and Health Act (OSKA) regulations 1972 and the Southern Standard Building Code 1973. Fire protection devices, where possible, are listed or approved by the Underwriters I.aboratories (UL) or FM.
1 i Materials of construction for the plant are fire resistive or noncombustible.
Where interior finishes are provided, such as in office or control room areas, these finishes ara noncombustible with flame spread ratings less than
- 25. A"rating of 25 or less is considered noncombustible by the National i Building Code. Pipe and duct insulation, including adhesives, are I noncombustible. Electrical cable jacketing is of the flame retardant, i
nonpropagating type. Building roof deck assemblies satisfy the requirements for FM Class 1 roof decks.
The plant is separated into various buildings, including: turbine building, j service building, control building, reactor building, diesel generator j building, fuel handling building, auxiliary building, intermediate building,
- water treatment building, radiological maintenance building, and auxiliary j service building. The separations between these buildings consist of three hour fire barriers with Class A three hour rated fire doors, fire dampers or other fire stops with the exception of the ceiling of the west penetration i access area which is of reinforced concrete on unprotected steel. Three hour j fire rated floor assemblies are provided in the control building.
1 i Estended vertical runs of cable trays which pass through non-rated floors and i ceilings are fire stopped with silicone RTV foaa to prevent propagation of j fire. Fire stops are provided at floor levels in the reactor building for cable trays which rise vertically more than 7 feet above the floor and then penetrata building walls.
9.5-1 AUGUST, 1988
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1 Stairways penetrating floors and elevators outside the reactor building are enclosed in one hour or two hour fire rated shaf*.s. Extensive vertical runs of cable trays are within three hour fire rated chases or are provided with fire stops or fire seals at each floor. In addition, high hazard equipment, such as the main turbine tube oil reservoir and pumps, are enclosed in three hour fire rated rooms. Ventilation system ducts are provided with two-1 1/2 hour or one-3 hour approved fire damper where these ducts penetrate 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire rated floors and walls. Hydrogen and other combustible gas manifolds are located outdoors. Smoke and heat would be vented as described in Section 5.0 of the Fire rcotection Evaluation Report.
Outdeor cransformers are separated from each other by fire walls where there is less than 50 feet of spatial separation. The outdoor transformers are provided with concrete pads, curbs, and trapped drainage to remo ' oil and water to a remote area. Outdoor transformer pads are filled to sna foot below the top of the curb with coarse crushed rock to limit the o.! iurface l area exposed to the atmosphere. In a similar fashion, concrete fis) s of building areas having oil lines or oil equipment are provided with trapped floor drains to ensure safe removal of oil and water. Building floor areas without oil hazards are provided with standard floor drains and/or sumps to remove fire water from fixed systems and hose streams. Equipment is mounted on pedestals.
The fire protection system is classified as non-nuclear safety class.
However, it is designed to ensure that operation or failure of any portion of the system does not produce unsafe conditions.
9.5.1.2 system Description l
9.5.1.2.1 Fire Protection Water Supply and Distribution System The fire protection water supply and distribution system, shown by Figura 9.5-1, provides fire protection water to the point of highest demand with one side o( the loop out of service. Fire protection water is supplied at an adequate pressure and in sufficient volume to supply the largest fixed fire pcotection system plus 1000 spe for hose streams. Alternatively. for a fire in a plant area containing satety related equipment, there is sufficient volume to supply the largest fixed fire protection system, plus 500 spm for hose streams, and 1000 sps for emergency diesel generator cooling.
i Monticello Reservoir is the water supply for the fire protection water supply i and distribution system.
The system includes one electric motor driven, 20 spa jockey pump to maintain l system pressure between 95 and 120 psig at all times. Two 2500 spm, UL listed, vertical centrifugal, turbine type fire pumps, located in the
- circulating water intake structure, supply water to the system. One of these i fire pumps is electric motor driven. The other, backup fire pump is dissol
- engine driven. Electric power for the electric motor driven pump is supplied
- from the normal station service bus. The diesel driven pump provides 100
! percent backup to the electric actor driven pump. Fuel oil for the diesel engint driven pump is supplied from an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> capacity fuel oil tank located outside the circulating water intake structure. Each fire pump is controlled by a UL listed controller.
AMENDMENT 2 9.5-2 AUGUST, 1986
l The electric motor driven fire pump starts automatically should system pressure drop to 95 psig. The diesel engine driven fire pump starts automatically at a system pressure of approximately 85 psig. Both pumps continue to operate until manually switched off.
Provisions are made for testing the operation of the fire pump through a fire service test connection outside the circulating water intake structure.
The fire protection water supply and distribution system includes a complete exterior, underground, yard hydrant loop, as well as an interior distribution piping system. Hydrants are provided at approximately 300 foot intervals along the loop and are approximately 50 feet from the buildings. Each hydrant has a hose house equipped with 250 feet of 2 1/2 inch fire hose, two combination spray nozzles and miscellar.sous tools and hose couplings. The interior distribution headers supply continuous flow hose reels, fire hose cabinets, and various water type, fixed, fire extinguiching systems. Each hose reel is equipped with 75 feet (or 100 feet) of 1-1/2 inch, noncollapsible, hard rubber, suction type hose and a fog nozzle. Each fire hose cabinet is equipped with 75 feet (or 100 feet) of 1-1/2 inch rubber lined fire hose and a fog nozzle. Interior and exterior distribution system piping is provid;d with adequate sectionalizing valves located at strategic positions in the system in order to permit maintenance on poetions of the system without shutting down the entire fire protection system.
9.5.1.4.2 Fire Detection and Alara System The fire detection and alarm system functions in conjunctiun with the plant security system in an integrated fire and security system. This system provides alarm information in each of three locationst the control room, tha security central alarm station, aad the security secondary alarm station.
Whenever a fire is detected, an audible signal is sounded and the location of the fire is annunciated at each location.
The system includes a digital computer at the security office and remote multiplexing units (RMU) near groups of alarm devices. Communication with the RMU's is by means of redundant loops which operate simultaneously.
Failure of one loop is alarmed. The system continues to function using the remaining loop.
Fire alarm signals are connected to the RMU's from local fire control panels by means of supervised c ,rguits which qualify for Class B operation in accordance with NFPA 72D 23 The fire detection systems used to actuate water suppression systems in safety rpl4 ted areas qualify for Class A operation in accordance with NFPA 72DL23 Local fire alarms are provided at the local fire control panels.
The fire detection and alarm system is designed to provide rapid and reliable detection and location of fires in their early stages.
Ionization type smoke detectors are located in many areas and rooms of the l i plant in order to provide early warning of a fire condition. The specific areas and rooms containing smoke detectors are shown on the fire protection evaluation drawings in the Fire Protection Evaluation Report.
AMENDMENT 2 9.5-3 AUGUST, 1986
In addition to the above .tystem, ionization type smoke detectors and high temperature alarms are provided in heating, ventilating and air conditioning l (KVAC) ducts at the discharges of fans. These alarms are connected to a separate alarm system on the HVAC control board in the control room.
Detection devices for fix4d fire protection systems are discubsed in the description of the individual systems. Such fire detection devices are connected to the integrated fire and security system. The integrated fire and security system also monitor.: the fire protection water supply and distribution system and arnunciates fire and trouble conditions in that system.
9.5.1.2.3 Carbon Dioulde Fixsd Fire Extinguishing Systems Carbon dioxide is used in the fixed fire extingaishing eystem for the relay room, computer room, and technical support cent er computer room at elevation 436'-0" in the control building. Carbon dioxide extinguishes fire by dilution of the oxygen concentration in the atmosphere to a level less than that required to support combustion (less than 12 volume percent).
Eatinguishing concentrations reduce the oxygen concentration below that required to support life. Therefore, special safety precautions are taken in areas where it is used, including alarms and time delay prior to discharge.
Equipment is provided to permit disarming a portion of the system that se rves
- an area which is to be occupied.
Areas subject to deep seated fires are provided with an adequate soaking period to ensure extinguishment. No decosposition products result from extinguishing a fire w The entire carbon dioxide system complieswithNFPA12Igthcarbondioxide.
1 The fixed carbon dioxide extinguishing system is automatically activated by heat-actuated detectors. In addition, each system is provided with a manual release capability.
9.5.1.2.'4 Raion 1301 Estinguishing Systes
- The permanent records storage room and telephone equipment room in the service building at elevation 436'-0" and the three individual rooms comprising the security computer roce in the control building at i elevation 436'-0" are protected by Halon 1301 eatingu.shing systans. These ,
systems are automatically actuated by ionization type smote detectors. '
Manual actuation by an electric breakglass station is provided at the entrance to each room.
9.5.1.2.5 Fixed Water Type Eatinguishing Systems Fixed water type extinguishing systems include automatic sprinkler systems, deluge water-svray systems and preaction sprinkler systaas. Automatic, vet pipe sprinkler systems are installed in the following areast l 1. Turbine building, below the operating and mezzanine floors.
- 2. Service building, elevation 436'-0" between column lines 101-113 and i
! elevation 448'-0" with the exception of rooms 104 and 118.
1 AMENDMENT 4 9.5-4 AUGUST, 1988
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- 3. Control building, elevation 412'-0" and elevation 436'-0" room 36-06 and 36-08 and 36-i2.
4 Diesel er.gine driven fire pump room in condenser circulating water intake screen and pumphouse.
- 5. Manual wet pipe sprinkler systems foe the compactor area and truck bay in the auxiliary building, floor elevation 436'-0" and 447'-0" and the security computer room in the control building, floor elevation 436'-0".
The piping network for all sprinkler systems, except the turbine building system below the operating floor, are sized for ordinary hazard occupancy in accordance with the NFPA piping schedule. The system below the turbine building operating floor is hydraulically calculated for a 0.30 spm/f t2 density over any area including the most remote 3000 ft2 and 0.20 GPM/ft2 over any 10,000 ft2 area. Each system, with the exception of the diesel engine driven fire pump room and compactor area and truck bay, includes an approved shutoff valve, alara valve and shutoff valve position switch. The diesel engine driven fire pump room sprinkler system is provided with an approved shutoff valve, valve position switch and a flow switch. The compactor area and truck bay is provided with an approved shutoff valve and valve position switch. These systems are designed to extinguish fires and control spread beyond the point of origin. Each system, with the exception of the compactor area and truck bay, provides a fire alarm signal upon the fusing of a sprinkler head and a trouble alare signal upon closure of the controlling shutoff valve.
i The compactor area and truck bay sprinkler systes provides a trouble alarm signal upon the opening of the controlling shutoff valve.
Hydraulically designed water spray systems, utillains directional solid cone or fog type spray nossles controlled by an approved deluge valve are provided for outside oil filled transformers and isolated phased bus ducts, the
, hydrogen seal oit unit., ventilating n;' stem charcoal filter plenuas, feedwater pumps (a turbine lubricating oil hasard area) and the south and west vall of the turbine building (adjacent to the transformer area). These systems are designed to wash down oil leakage, cool equipment, protect equipment exposed
! to fires and eatinguish fires. Transformer and oil equipment water spray a systems are automatically activated by heat-actuated detectors and may be actuated manually at strategically located pull stations. Charcoal filter j plenums have a thermistor sensor imbedded in the charcoal which actuates i
alarms upon detection of a bed temperature of 2550F and again at 3100F, whicn is less than the spontaneous ignition temperature of the charcoal. The charcoal water spray syster can be initiated manually if the temperature cannot be controlled by other means.
Automatic preaction sprinkler systems are provided to protect the followingt
- 1. The diesel generator building.
- 2. The control building, cable spreading rooms at elevation 425'-0" and 448'-0", and the cable chases at elevation 400'-0", 412'-0", 436'-0",
and 463'-0".
AMENDM WT 4 9.5-5 AUGUST, 1988
- 3. Service water pumphouse - service water pump room, floor elevation 436'-0" and service water pumphouse supply fan rooms, floor elevation ;
441'-0".
! 4. Intermediate building, floor elevation 412'-0", rooms 12-02. 12-10,
!12-13A, 12-138,12-13C, and floor elevation 436'-0" area approximately between column lines 6.8 and 8.3. !
, 5. Auxiliary building, floor elevation 463'-0", between column lines 9.5 and 8.8 and column lines M and J. i l
A manual preaction sprinkler system is provided for the turbine generator [
, bearings. The system is hydraulically calculated for a water application t rate of at least 0.25 GPM/fg2 of the protected surface area.
j The proaction sprinkler system piping supplying the sprinklers is supervised
! with air pressure so that a trouble alarm will sound if a pipe break or leak occurs. Water will not discharge from these systems without operation of a i heat or smoke detector and melting of a fusible link (with the exception of j the turbine generator bearing deluge system which also requires manual operation of the deluge valve).
9.5.1.2.6 Portable Fire Protection Equipment Portable fire extinguishers of the water, carbon dioxide and dry chemical
! types are provided for use on small fires. These extinguishers are selected and located in accordance with NFPA Standards.
j 9.5.1.3 System Evataation
, The fire protection system is designed to ensure that operation or failure of j any portion of the system does not produce an unsafe condition. Areas where i
fire protection water could be released by system operation or a system j failure are provided with floor drains and/or sumps. Critical equipment is support'ed above the normal floor elevation to prevent damage due ta flooding.
! Special attention is given to sizing and routing of fire water lines to
, minimise exposure of safety class equipment. Each redundant charcoal filter
! is protected by its own independent fire protection system. Failure of the l fire protection system for one safety-related system does not affect the j operation of another safety-related system.
1 j A failure mode and effects analysis of the fire protection and detection
! systems and major components is presented in Table 9.5-1. Where "Fire alarm"
- and "Trouble alarm" are esed in the effect column, these terms refer to an i alarm condition on the fire alarm CRT in the control room. "No Effect" is
! used to mean that the mode of failure does not affect plant safety or prevent fire protection system operation unless indicated otherwise.
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9.5.1.4 Inesection and Testina geovirements I
! Administrative controls are provided through existing Plant Administrative l and Operating Procedures, and the Operations Quality Assurance Program to AMENDMENT 2 9.5-6 AUGUST, 1986
ensure that the Fire Protection Program and equipment is properly maintained.
This includes QA audits of the program implementation, condJCC of periodic test inspections, and remedial actions for systems and barriers out of service. This program emphasizes those elements of fire protection that are associated with safe shutdown as described in the Fire Protection Evaluation Report and their significance when evaluating program and equipment deficiencies.
l All fire protection equipment and systems for areas containing safety related equipment are subjected to a complete inspection and acceptance test to I demonstrate conformance with functional design criteria after installation is completed. Periodic inspections and tests are conducted as prescribed by Technical Specifications / Station Administrative procedures.
l Fire pumps are inspected and tested periodically at 150 percent of rated pump capacity. The diesel driven pump is run periodically to bring it to normal operating temperature and pressure and ensure proper operation at rated speed.
i l Fire alarm and detection systems are subjected to "spot" tests and inspection j on a periodic basis.
Carbon dioxide and Halen 1301 extinguishing systems are inspected and tested on a periodic basis. Inspection and test does not involve actual discharge of the gaseous agent.
Inspection and 2 inch drain tests are conducted on all wet pipe sprinkler systems on a poriodic basis to ensure that the water supply is available.
Water spray deluge systems are inspected and flow tested, where possible, on a periodic basis to ensure proper nosale positions and adequate water pressures. Deluge spray systems for the charcoal filters are subjected to a periodic 2 inch drain test to ensure that water is present at the delug,e valve. Visual inspection of these systems is also performed periodically.
Fire eatinguishers and hose reels are inspected periodscally to ensure they are in operating condition. Extinguishers are also subjected to a hydrostatic test at regular intervals.
Equipment out of service including fire suppression, detection, and barriers will be controlled through the administrative program and appropriate remedial actions taken. The program requires all impairments to fire protection system to be identified and appropriate notification given to the Fire Protection Engineer for evaluation. Based on the condition, engineering analysis say be required to dete<mine the extent of the fire hazard to safe plant operations. As conditions warrant, remedial actions would include compensatory measures to ensure equivalent level of fire protection in addition to timely efforts to effect repairs and restore equipment to service.
AMENDMENT 3 9.5-7 AUGUST. 1987
9.5.1.5 Personnel Qualification and Trainina SCE4C and the fire protection consultant are qualified by training and experience to successfully undertake the design function and are either members or qualified to hold membership grade in the Society of Fire Protection Engineers.
l The responsibility for training and maintaining the competence of fire fighting personnel rests with and is assumed by SCE&C.
9.5.2 L M ICATIONS SYSTEMS 9.5.2.1 Desian Bases The communication systems are designed to provide reliable communications between all essential areas of the station, and to essential locations remote from the plant during normal operations or under emergency conditions. This capability is provided by diverse types of communication systems.
9.5.2.2 Description 9.5.2.2.1 Intra-Plant Coansunications The intra plant communications network consists of the following systemst
- 1. A page/ party public address with evacuation alarms and a fire alarm.
- 2. A maintenance communicatior.s system.
AMENDMENT 2 9.5-7a AUGUST. 1986
for the life of the plant. This long-term maintenance program uses the concept of a shutdown "path" for each fire area, zone, or subsone. It also uses the analysis technique of comparing the list of equipment and cables required by a specific shutdown path to the list of equipment. and cables located in the fire area, zone, or subcone for which the path is to be used.
Equipment that needed modification to ensure compliance was identified during the analysis and documented. R: quests for plant modifications were developed from these documents and described in the May 29, 1985, letter from SCE&C to Mr. H. R. Denton, NRR, and supplemented by letters dated September 16, 1985, September 20, 1985, and April 23, 1986.
The rext step was to develop exemption requests based on the identified potential deviations as described in the SCE&C letters dated
. H. R. Denton, NRR.
The final step was the development of Plant Emergency Procedures to bring the plant to stable hot standby and subsequently to cold shutdown.
Fire Emergency Procedures FEP-1.0 and FEP-1.1 are the procedures to be used in the event of a control room evacuation and to bring the plant to cold shutdown within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Additional procedures are being developed to provide specific direction for shutdown from the control room in the event of a major fire in general plant areas. These procedures are being based on the shutdown "path" identified for each fire area, zone, or subzone, and on the results of the analysis
.. including the identified resolutions of potential deviations. These procedures will be revised once all plant modifications have been insta,lled.
3.
1.6 CONCLUSION
SCE&C considers that this method of analysis ar.d the resulting documentation provide an adequate demonstration of the compliance of the Virgil C. Summer Nuclear Station with the criteria of 10CFR50, Appendix R. The results are presented in Section e.6 of this report.
3.1-5
i VIRGIL C. SUMER NUCLEAR STATION !
FSAR/FPER REVISION NOTICE '
DESCRIPTION:
Ag,/,v44 c@ 4n4/d da .o f MM y J ffw No. 13o
[ !
! Date y /a h r 1 4
4 i
AFFECTED FSAn/FPER SECTION:
- 3. /. s~. ^
us e .3 . / - S~
JUSTlFICATION FOR CHANGE:
) jfe l/d S&< a/b- J/sy; pow l4 fACsf
! Does change involve plant design as described in F5AR/FPER7 Does change involve procedures described in FSAR/FPER? Yes Yes No [
No y _
Does change involve tests and experiments not described in FSAR/FPER? l I
Yes No / l 50.544 Review Required Yes No / i i
50.544 Review Completed Yes No <
l 50.59 Review Required Reference j 50.59 ReviewCompleted Yes 7 No Yes - No Reference
' Tech. Spec. Change Required Yes , No e '
50.59 Summary Paragraph Req'd Yes < , No
) Submit to PSRC for Review Yes / No l !
i OTHER AFFECTED DOCUMENTS: i l MRF sv/A [
l I
I l SCf&G REVIEW:
i Review OTHER ORGANIZATION REVIEW: !
j Review t, -
Rea'd initials Rec'd ng, ervices*
! < initials /FCN No.
Nh
{
Nuc. Plant Operations QA ./ h y%w W !
[
- QC !
! G/C
' Nuc. Ops. Ed. & Trng. {
Health Physics !
Nuc, Securit D&M i
- Core Eng. y
j Other A j I 1
- Design Basis Document Revision Required. LICE N AL t
f Yes No /
/ '
Pbfl!)
{
"5eMicrYngineer f ,Cate Regulatory lnterface
(
(
A_Y Manag L d.;fR j Date ;
[ Nuclea censing l
EXHIBITI 1 4
- NL101 !
REVISION 10 l
. - - - , _ , - - - - , , , . . - , _ - . - --.--,.,_ --- --- .- -.---.--------.-. -t
for the life of the plant. This long-term maintenance program uses the concept of a shutdown "path" for each fire area, sone, or subacne. It also uses the analysis technique of comparing the list of equipment and '
cables required by a specific shutdown path to the list of equipment and cables locatet in the fire area, sone, or subsone for which the path is to be used.
Equipment that needed modification to ensure compliance was identified during the analysis and documented. Requests for plant modifications were developed from these documents and described in the May 29, 1985, letter from SCE40 t.o Mr. W. R. Denton, WRR, and supplemented by letters dated September 16, 1985, September 20, 1985, and April 23, 1986.
The next step was to develop exemption requests based on the identified potential deviations as described in the SCE&C letters dated May 29, 1985, and April 23, 1986 to Mr. W. R. Denton, NRA.
, A d*f
- I,eg l The final step was the development of Plant Emergency Procedures to bring the plant to stable hot standby and subsequently to cold shutdown.
I Fire Emergency Procedures FEP-1.0 and FEP 1.1 are the procedures to be used in the event of a control room evacuation and to bring the plant to cold shutdown within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Additional procedures are being developed to provide specific direction for shutdown from the control room in the event of a major fire in general plant areas. Dese i
procedures are being based on the shutdown "path" identified fer esca fire area, sone, or subsone, and on the results of the analysis
.. including the identified resolutions of potential deviations. These i procedures will be revised once all plant modificstions have been l inst,alled.
1 3.1.6 CoelCLUS10tf !
- SCE&C considers that this method of analysis and the resulting documentation provide an adequate demonstration of the compliance of the Virgil C. Summer Nuclear Station with the criteria of 10CFR50, Appendix R. The results are presented in Section 4.0 of this report.
~
- l' *
- *MA/*cleA A,s .L& we e
& ^ * ' ~ /< % , M <.9 Q
i,<y $ i m, ,
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- 4 ~ % ! m J p t p y i e r i.
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3.1-5
\ ._
1 SAMPLE VIRGIL C. SUMMER NUCLEAR STATION a
10CFR50.59 YVALUATION ANALYSIS AMICfIO DOCUMim0.Md Check Aoplicable Yes [ ] and No ( ) Indications Does this modification change the Final Safety Analysis Report or Fire Protection Evaluation Report?
TECH. SPEC. R E FE RENCE FPENFMA REFERENCE 5ection Page yes(d No( ) Chapter Section Page a '2 7 f. f 3. /-S~
is a change in Tech.
5 0ecificationsinvolved?
ch 5p cs.' O Yes[ ] No( Not addressed in
_ F5ANFPER ( )
" o UNREVIEWED 5AFETY QUESTION EVALUATION: Answer the following questions with a *yes" or "no", and provide specific reasons just4fying the decision. (Attach additional
/ sheets as tequired.)
Nuc. Lic. Reviewer 5aio 1. N the probability of an occurrence, the consequences of an accident, or malfunction of safety related equipment ,
as previously eval ated in the FSARincreased?
Yes [ ] No (
, P5aC/N5RC 2. Is the possibility of an acciderit or malfunction of a Review diHerent type than any previously evaluated in the F5ARincrease f Yes [ ] No ([d?
- 3. Is the margin of safety as defined in the basis for any Request and Receive Tech 5pe:. reduc d? ,
Nuclear Regulatory Yes [ ] No ( '
Commission Authorization For Change Prior 4/,,M1,,L ,,6 /,fr ,W# ~
Th implementation a M/l .J "- /#- ~ /, ,
Of the Subject Change E o4%(m /_ A r s f4 6 r -
0 Authorization Deleted
% Any Antwer Yes ( ) All Answers No ([
o ,
'3 ) o Abort _
Author Iation _
initiate asign Cha#qe
~
- Design Change Received j
'If either answert (2) or (3) are *yes", then the change is
- ptV ".
7 E4neer submitted to the NRC unoer 10CFR50 59. If answer (1)is "yes' tnt answers (2) and (3) are "no", then the change eportable uncer 10CFR50.59b and a destnption of the p[9 - - -
/ k//4 incepencent Reviewer Date
.nge will be included in the Annual Report. All other changes are not reportable. / '
kid' tiate Manager /Supervirar Date EXHIBIT 111 ruuvu
.1 +
OjSTRIBUTIONFORHEETING
SUMMARY
DATED: SEP 2 619M f a cility: V. C. Sumer Nuclear Stetion
- Docket File hRC POR Local POR P0ll-1 Reading E. Adensam P. Anderson J. Hayes OGC E. Jordan (MNBB3302)
- 8. Grires (9A2)
O. Kubicki (8H7)
ACRS (10)
B. Troskoski (17019) cc: Licensee / Applicant Service List 1
)
0Fol
'is