ML022470190

Virgil C Summer Unit 1, Technical Specification Pages for Amendment 160 Spent Fuel Pool Expansion

ML022470190
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Site:	Summer
Issue date:	08/30/2002
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Valves ....................................................................................... 3/4 7-1 Emergency Feedwater System ............................................................. 3/4 7-4 Condensate Storage Tank .................................................................... 3/4 7-6 Activity .................................................................................................. 7-7 Main Steam Line Isolation Valves ......................................................... 3/4 7-9 Feedwater Isolation Valves ................................................................... 3/4 7-9a STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION ..... 3/4 7-10 3/4.7.2 3/4.7.3 COMPONENT COOLING WATER SYSTEM ........................................ 3/47-11 SERVICE WATER SYSTEM ................................................................ 3/4 7-12 3/4.7.4 3/4.7.5 ULTIMATE HEAT SINK ........................................................................ 3/4 7-13 CONTROL ROOM NORMAL AND EMERGENCY AIR HANDLING SYSTEM. 3/47-14 3/4.7.6 SNUBBERS .......................................................................................... 3/47-16 3/4.7.7 SEALED SOURCE CONTAMINATION ................................................ 3/4 7-23 3/4.7.8 AREA TEMPERATURE MONITORING ................................................ 3/4 7-37 3/4.7.9 WATER LEVEL - SPENT FUEL POOL ................................................ 3/4 7-39 3/4.7.10 SPENT FUEL POOL VENTILATION SYSTEM ..................................... 3/4 7-40 3/4.7.11 SPENT FUEL ASSEMBLY STORAGE ................................................. 3/4 7-42 3/4.7.12 SPENT FUEL POOL BORON CONCENTRATION ............................... 3/4 7-44 3/4.7.13 Vill Amendment No. 23,79, 160 SUMMER - UNIT 1

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS PAGE SECTION 3/4.9 REFUELING OPERATIONS 3/4 9-1 3/4.9.1 BORON CONCENTRATION ................................................................

INSTRUMENTATION ........................................................................... 3/4 9-2 3/4.9.2 DECAY TIM E ....................................................................................... 3/4 9-3 3/4.9.3 REACTOR BUILDING PENETRATIONS .............................................. 3/4 9-4 3/4.9.4 COMMUNICATIONS ............................................................................ 3/4 9-5 3/4.9.5 MANIPULATOR CRANE ...................................................................... 3/4 9-6 3/4.9.6 3/4.9.7 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION High W ater Level ................................................................................. 3/4 9-7 Low W ater Level ................................................................................... 3/4 9-8 3/4 9-9 3/4.9.8 REACTOR BUILDING PURGE AND EXHAUST ISOLATION SYSTEM ....

WATER LEVEL - REFUELING CAVITY AND FUEL TRANSFER CANAL. 3/4 9-10 3/4.9.9 3/4.10 SPECIAL TEST EXCEPTIONS SHUTDOWN MARGIN ......................................................................... 3/4 10-1 3/4.10.1 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS 3/4 10-2 3/4.10.2 PHYSICS TESTS ................................................................................. 3/4 10-3 3/4.10.3 REACTOR COOLANT LOOPS ............................................................ 3/4 10-4 3/4.10.4 POSITION INDICATION SYSTEM - SHUTDOWN ............................... 3/4 10-5 3/4.10.5 X Amendment No. 4-9 160 SUMMER - UNIT 1

INDEX BASES SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYC LE ................................................................................. B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE/TEMPERATURE LIMITATION ..... B 3/4 7-3 3/4.7.3 COMPONENT COOLING WATER SYSTEM ........................................ B 3/4 7-3 3/4.7.4 SERVICE WATER SYSTEM ................................................................ B 3/4 7-3 3/4.7.5 ULTIMATE HEAT SINK ........................................................................ B 3/4 7-3 3/4.7.6 CONTROL ROOM NORMAL AND EMERGENCY AIR HANDLING SYSTEM ............................................. B 3/4 7-4 3/4.7.7 SNUBBERS .......................................................................................... B 3/4 7-4 3/4.7.8 SEALED SOURCE CONTAMINATION ................................................ B 3/4 7-6 3/4.7.9 AREA TEMPERATURE MONITORING ................................................ B 3/4 7-6 3/4.7.10 WATER LEVEL - SPENT FUEL POOL ................................................ B 3/4 7-6 3/4.7.11 SPENT FUEL POOL VENTILATION SYSTEM ..................................... B 3/4 7-6 3/4.7.12 SPENT FUEL ASSEMBLY STORAGE ................................................. B 3/4 7-7 3/4.7.13 SPENT FUEL POOL BORON CONCENTRATION ............................... B 3/4 7-7 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1, 3/4.8.2 and 3/4.8.3 A.C. SOURCES, D.C. SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS ................................................... B 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTION DEVICES ......................... B 3/4 8-3 SUMMER - UNIT 1 XIV Amendment No. 38,63, 79, 160

INDEX BASES SECTION PAGE 3/4.9 REFUELING OPERATIONS B 3/4 9-1 3/4.9.1 BORON CONCENTRATION ................................................................

B 3/4 9-1 3/4.9.2 INSTRUM ENTATIO N ..........................................................................

B 3/4 9-1 3/4.9.3 D ECAY TIM E .......................................................................................

B 3/4 9-1 3/4.9.4 REACTOR BUILDING PENETRATIONS .............................................

B 3/4 9-1 3/4.9.5 CO MM UNICATIO NS ...........................................................................

B 3/4 9-2 3/4.9.6 MANIPULATOR CRANE ......................................................................

B 3/4 9-2 3/4.9.7 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION ...........

B 3/4 9-2 3/4.9.8 REACTOR BUILDING PURGE AND EXHAUST ISOLATION SYSTEM .....

B 3/4 9-2 3/4.9.9 WATER LEVEL - REACTOR VESSEL ........................................................

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOW N MARGIN ........................................................................ B 3/4 10-1 B 3/4 10-1 3/4.102 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS B 3/4 10-1 3/4.10.3 PHYSICS TESTS ................................................................................

B 3/4 10-1 3/4.10.4 REACTOR COOLANT LOOPS ............................................................

B 3/4 10-1 3/4.10.5 POSITION INDICATION SYSTEM - SHUTDOWN ...............................

SUMMER - UNIT 1 XV Amendment No. 49 "160

PLANT SYSTEMS 3/4.7.10 WATER LEVEL-SPENT FUEL POOL LIMITING CONDITION FOR OPERATION fuel assemblies 3.7.10 At least 23 feet of water shall be maintained over the top of irradiated seated in the storage racks.

APPLICABILITY: Whenever irradiated fuel assemblies are in the spent fuel pool.

ACTION:

movement of fuel With the requirements of the above specification not satisfied, suspend all restore the water assemblies and crane operations with loads in the fuel storage areas and level to within its limit within 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br />.

SURVEILLANCE REQUIREMENTS to be at least its minimum 4.7.10 The water level in the spent fuel pool shall be determined are in the spent fuel required depth at least once per 7 days when irradiated fuel assemblies pool.

3/4 7-39 Amendment No. 160 SUMMER - UNIT 1

PLANT SYSTEMS 3/4.7.11 SPENT FUEL POOL VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.11 Two independent spent fuel pool ventilation sub-systems shall be OPERABLE with at least one sub-system in operation.

APPLICABILITY: Whenever irradiated fuel is being moved in the spent fuel pool and during crane operation with loads over the pool.

ACTION:

a. With one spent fuel pool ventilation sub-system inoperable, fuel movement within the spent fuel pool or crane operation with loads over the spent fuel pool may proceed provided the OPERABLE spent fuel pool ventilation sub-system is capable of being powered from an OPERABLE emergency power source and is in operation and discharging through at least one train of HEPA filters and charcoal adsorbers.

b. With no spent fuel pool ventilation sub-system OPERABLE, suspend all operations involving movement of fuel within the spent fuel pool or crane operation with loads over the spent fuel pool.

c. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.11 The above required spent fuel pool ventilation sub-systems shall be demonstrated OPERABLE:

a. At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that each sub-system operates for at least 15 minutes.

b. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical -release in any ventilation zone communicating with the system by:

1. Verifying that the cleanup system satisfies the in-place testing acceptance criteria and uses the test procedures of Regulatory Positions C.5.a, C.5.c and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 30,000 ACFM +/- 10%.

SUMMER - UNIT 1 3/4 7-40 Amendment No. 42, 159, "160

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

2. Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of ASTM D3803-1989, at a relative humidity of 95%

and 30 0C with a methyl iodide penetration of <2.5%.

3. Verifying a system flow rate of 30,000 ACFM +/- 10% during system operation when tested in accordance with ANSI N510-1975.

c. Prior to the movement of fuel or crane operation with loads over the pool by verifying that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of ASTM D3803-1989, at a relative humidity of 95% and 30 0C with a methyl iodide penetration of <2.5%.

Subsequent to each initial analysis (which must be completed prior to fuel movement or crane operation with loads over the pool), during the period of time in which there is to be fuel or crane movement with loads over the pool, verify charcoal adsorber operation every 720 hours30 days <br />4.286 weeks <br />0.986 months <br /> by obtaining and analyzing a sample as described above. These subsequent analyses are to be completed within thirty one (31) days of sample removal.

d. At least once per 18 months by:

1. Verifying that the pressure drop across the combined HEPA and roughing filters and charcoal adsorber banks is less than 6 inches Water Gauge while operating the system at a flow rate of 30,000 ACFM +/- 10%.

2. Verifying that on a loss of offsite power test signal, the system automatically starts.

3. Verifying that the system maintains the spent fuel pool area at a negative pressure greater than or equal to 1/8 inches Water Gauge relative to the outside atmosphere during system operation.

e. After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99.95% of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the system at a flow rate of 30,000 ACFM +/- 10%.

f. After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99.95% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the system at a flow rate of 30,000 ACFM +/- 10%.

SUMMER - UNIT 1 3/4 7-41 Amendment No. 42, !31, 440,159,160

PLANT SYSTEMS 3/4.7.12 SPENT FUEL ASSEMBLY STORAGE LIMITING CONDITION FOR OPERATION 3.7.12 The combination of initial enrichment and cumulative burnup for spent fuel assemblies stored in Region 2 shall be within the acceptable domain of Figure 3.7-1.

APPLICABILITY: Whenever irradiated fuel assemblies are in the spent fuel pool.

ACTION:

a. With the requirements of the above specification not satisfied, suspend all other movement of fuel assemblies and crane operations with loads in the fuel storage areas and move the non-complying fuel assemblies to Region 1. Until these requirements of the above specification are satisfied, boron concentration of the spent fuel pool shall be verified to be greater than or equal to 2000 ppm at least once per 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br />.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS by careful 4.7.12 The burnup of each fuel assembly stored in Region 2 shall be ascertained analysis of its burnup history prior to storage in Region 2. A complete record of such analysis fuel shall be kept for the time period that the ioel assembly remains in Region 2 of the spent pool.

SUMMER - UNIT 1 3/4 7-42 Amendment No. 27,116, 160

45 40 35 z

0 30 25 W

20 0

2 ca 15 Cfo 10 W

0o 5

0QL1 2.0 2.5 3.0 3.5 4.0 4.5 5.0 MAXIMUM NOMINAL U-235 ENRICHMENT (W/0) burn-up Notes: 1. Fuel assemblies with enrichments less than 2.0 W/0 must meet the requirements of 2.0 W/0 U-235 assemblies.

2. Use of the following polynomial fit is acceptable, where E = Enrichment (W/O):

3 Assembly Discharge Burnup = 0.1246 E - 1.91 E + 20.9205 E - 30.2482 2

FIGURE 3.7-1 REQUIRED FUEL ASSEMBLY BURN-UP AS A FUNCTION OF INITIAL ENRICHMENT TO PERMIT STORAGE IN REGION 2 3/4 7-43 Amendment No. 160 SUMMER - UNIT 1

PLANT SYSTEMS 3/4.7.13 SPENT FUEL POOL BORON CONCENTRATION LIMITING CONDITION FOR OPERATION canal, and the cask 3.7.13 The boron concentration in the spent fuel pool, the fuel transfer than or equal to 500 ppm.

loading pit shall be maintained at a boron concentration greater APPLICABILITY: Whenever new or irradiated fuel is being moved (non-refueling pit.

movement) in the spent fuel pool, fuel transfer canal, or cask loading ACTION:

fuel assemblies and With the requirements of the above not satisfied, suspend all movement of canal, and the cask loading crane operations with loads in the spent fuel pool, the fuel transfer fuel is being moved shall be verified greater pit until the boron concentration in the area where than or equal to 500 ppm.

SURVEILLANCE REQUIREMENTS canal, or cask loading pit 4.7.13 The boron concentration of the spent fuel pool, fuel transfer hours when moving new or shall be determined by chemical analysis at least once per 72 loading pit.

irradiated fuel in the spent fuel pool, transfer canal, or cask 3/4 7-44 Amendment No.

SUMMER - UNIT 1 "160

REFUELING OPERATIONS 3/4.9.3 DECAY TIME LIMITING CONDITION FOR OPERATION within the acceptable domain of Figure 3.9.3 The reactor shall be subcritical a period of time 3.9-1, but not less than 72 hours3 days <br />0.429 weeks <br />0.0986 months <br />.

vessel.

APPLICABILITY: During movement of irradiated fuel in the reactor pressure ACTION:

suspend all movement of With the reactor subcritical for less than 72 hours3 days <br />0.429 weeks <br />0.0986 months <br />, immediately subcritical for greater than 72 irradiated fuel in the reactor pressure vessel. With the reactor immediately suspend movement of hours but not within the acceptable domain of Figure 3.9-1, irradiated fuel in the reactor pressure vessel.

SURVEILLANCE REQUIREMENTS subcritical for a period of time within the 4.9.3.1 The reactor shall be determined to have been date and time of subcriticality prior to acceptable domain of Figure 3.9-1 by verification of the movement of irradiated fuel in the reactor pressure vessel.

pressure vessel, and at least once 4.9.3.2 Prior to moving irradiated fuel from the reactor the CCW temperature at the inlet to every 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> during movement of irradiated fuel, verify the acceptable domain of Figure the Spent Fuel Pool Cooling System heat exchanger is within 3.9-1.

3/4 9-3 Amendment No.160 SUMMER - UNIT 1

150 140 130 03 rr 0D 120

-r I- 110 0

w 100 0

K*

90 0

Y 80 70' 60 85 95 100 105 CCW TEMPERATURE (OF)

Note: The use of linear interpolation between CCW temperatures incore reported above is acceptable to determine the minimum hold time.

FIGURE 3.9-1 REQUIRED IN-CORE HOLD TIME AS A FUNCTION OF COMPONENT COOLING WATER (CCW) TEMPERATURE 314 9-3a Amendment No.'160 SUMMER - UNIT 1

PLANT SYSTEMS BASES 3/4.7.8 SEALED SOURCE CONTAMINATION sources requiring leak testing, The limitations on removable contamination for 70.39(c) limits for plutonium. This limitation will including alpha emitters, is based on 10 CFR special nuclear material sources will not ensure that leakage from byproduct, source, and are classified into three groups according exceed allowable intake values. Sealed sources with the probability of damage to to their use, with surveillance requirements commensurate handled are required to be are frequently a source in that group. Those sources which are not. Sealed sources which are continuously tested more often than those which sources within radiation monitoring or enclosed within a shielded mechanism (i.e. sealed stored and need not be tested unless they boron measuring devices) are considered to be are removed from the shielded mechanism.

3/4.7.9 AREA TEMPERATURE MONITORING safety-related equipment will not be The area temperature limitations ensure that qualification temperatures.

subjected to temperatures in excess of their environmental equipment and can cause a loss of0 its Exposure to excessive temperatures may degrade an allowance for instrument error of 2 F.

OPERABILITY. The temperature limits include POOL 3/4.7.10 WATER LEVEL - SPENT FUEL that sufficient water depth is The restrictions on minimum water level ensure iodine gap activity released from the rupture available to remove 99% of the assumed 10%

water depth is consistent with the assumptions of an irradiated fuel assembly. The minimum of the accident analysis.

3/4.7.11 SPENT FUEL POOL VENTILATION SYSTEM system ensure that all radioactive The limitations on the spent fuel pool ventilation will be filtered through the HEPA filters material released from an irradiated fuel assembly the atmosphere. The OPERABILITY of this and charcoal adsorber prior to discharge to are consistent with the assumptions of the system and the resulting iodine removal capacity accident analysis.

Amendment No. 7-9, 160 B 3/4 7-6 SUMMER - UNIT 1

PLANT SYSTEMS BASES 3/4.7.12 SPENT FUEL ASSEMBLY STORAGE The restrictions placed on spent fuel assemblies in Region 2 of the spent fuel pool ensure Poison Rod Ke~f remains less than 0.95. The minimum burnup bounds the use of Burnable Assemblies (BPRA), Wetted Annular Burnable Absorbers (WABA), Integral Fuel Burnable Absorbers (IFBA), and Erbia.

An axial burnup shape penalty is also included in the burnup requirement.

3/4.7.13 SPENT FUEL POOL BORON CONCENTRATION A minimum boron concentration is required in the spent fuel pool, fuel transfer canal, or cask 0.95 loading pit whenever new 4.95 W/0 fuel is being moved to ensure Keff remains less than during this normal condition of fuel movement.

The minimum boron concentration in the spent fuel pool, fuel transfer canal, or cask loading pit also is sufficient to maintain Keff less than 0.95 for postulated accident condition result consisting of a dropped or a mispositioned fuel assembly. This requirement is a direct the Spent Fuel of the analysis performed for pool criticality during evolutions performed while being Pool is isolated from the reactor cavity and is due to geometry, materials and poisons different in the spent fuel pool than those in the reactor. During periods of direct when communication between the pool and the reactor, Specification 3.9.1 shall be followed the refueling cavity is filled and the transfer canal blind flange is removed.

Sampling to determine boron concentration is required only for those specific areas where fuel is being moved, e.g. in the spent fuel pool, in the fuel transfer canal, or in the cask loading area.

B 3/4 7-7 Amendment No. 2 160 SUMMER - UNIT 1

3/4.9 REFUELING OPERATIONS BASES 3/4.9.1 BORON CONCENTRATION ensure that: 1) the reactor The limitations on reactivity conditions during REFUELING and 2) a uniform boron concentration is will remain subcritical during CORE ALTERATIONS, having direct access to the reactor maintained for reactivity control in the water volume conditions assumed for the boron vessel. These limitations are consistent with the initial of 0.95 or less for Keff includes a 1 dilution incident in the accident analyses. The value Similarly, the boron concentration percent delta k/k conservative allowance for uncertainties. allowance of 50 ppm uncertainty value of 2000 ppm or greater includes a conservative to be closed to minimize the boron. Valves in the reactor makeup system are required possibility of a boron dilution accident.

3/4.9.2 INSTRUMENTATION monitors ensures that redundant The OPERABILITY of the source range neutron flux in the reactivity condition of the core.

monitoring capability is available to detect changes 3/4.9.3 DECAY TIME prior to movement of The minimum time of 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> for reactor subcriticality ensures that sufficient time has irradiated fuel assemblies in the reactor pressure vessel fission products. The minimum elapsed to allow the radioactive decay of the short-lived used in the accident analysis.

decay time of 72 hours3 days <br />0.429 weeks <br />0.0986 months <br /> is consistent with the assumptions Cooling Water (CCW)

The tabulated hold times associated with Component is reduced sufficiently to allow the spent temperature ensure that the spent fuel heat load 0 temperature below 170 F. These hold fuel pool cooling system to maintain the bulk pool the Spent Fuel Pool under the highest times ensure that adequate cooling is provided to based on the performance of the cooling possible heat load conditions. The hold times are and recognizes that the spent fuel pool system, which is dependent upon CCW temperature to 2400 gpm during single loop cooling system is capable of increased flow rates up only a single cooling loop is operable operation. This higher flow rate may be required when during a refueling outage.

are adjusted for uncertainty in The CCW temperature limits defined in Figure 3.9-1 the implementing procedure.

3/4.9.4 REACTOR BUILDING PENETRATIONS closure and OPERABILITY ensure The requirements on reactor building penetration will be restricted from leakage to the that a release of radioactive material within containment are sufficient to restrict radioactive environment. The OPERABILITY and closure restrictions upon the lack of reactor building material release from a fuel element rupture based MODE.

pressurization potential while in the REFUELING 3/4.9.5 COMMUNICATIONS ensures that refueling station The requirement for communications capability changes in the facility status or core personnel can be promptly informed of significant reactivity conditions during CORE ALTERATIONS.

Amendment No. 160 SUMMER - UNIT 1 B 3/4 9-1

REFUELING OPERATIONS BASES 3/4.9.6 MANIPULATOR CRANE The OPERABILITY requirements for the manipulator cranes ensure that:

1) manipulator cranes will be used for movement of control rods and fuel assemblies,

2) each crane has sufficient load capacity to lift a control rod and fuel assembly, and

3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

3/4.9.7 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirement that at least one residual heat removal loop be in operation ensures that 1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140OF as required during the REFUELING MODE, and 2) sufficient coolant circulation is maintained thru the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification.

The requirement to have two RHR loops OPERABLE when there is less than 23 feet of water above the reactor pressure vessel flange ensures that a single failure of the operating RHR loop will not result in a complete loss of residual heat removal capability.

With the reactor vessel head removed and at least 23 feet of water above the reactor pressure vessel flange, a large heat sink is available for core cooling. Thus, in the event of a failure of the operating RHR loop, adequate time is provided to initiate emergency procedures to cool the core.

3/4.9.8 REACTOR BUILDING PURGE SUPPLY AND EXHAUST ISOLATION SYSTEM The OPERABILITY of this system ensures that the reactor building vent and purge penetrations will be automatically isolated upon detection of high radiation levels within the of reactor building. The OPERABILITY of this system is required to restrict the release radioactive material from the reactor building atmosphere to the environment.

3/4.9.9 WATER LEVEL - REACTOR VESSEL The restrictions on minimum water level ensure that sufficient water depth is the rupture available to remove 99% of the assumed 10% iodine gap activity released from of an irradiated fuel assembly. The minimum water depth is consistent with the assumptions of the accident analysis.

Amendment No. 160 SUMMER - UNIT 1 B 3/4 9-2

DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The core shall contain 157 fuel assemblies. Each fuel assembly shall consist of 264 Zircaloy-4 or ZIRLO(TM) clad fuel rods with an initial composition of uranium dioxide with a maximum nominal enrichment of 4.95 weight percent U-235 as fuel material. Limited substitutions of Zircaloy-4, ZIRLO(TM) and/or stainless steel filler rods for fuel rods, if justified by a cycle specific reload analysis using an NRC-approved methodology, may be used. Fuel assembly configurations shall be limited to those designs that have been analyzed with applicable NRC staff-approved codes and methods, and shown by tests or cycle-specific reload analyses to comply with all fuel safety design bases. Reload fuel shall contain sufficient integral fuel burnable absorbers such that the requirements of Specifications 5.6.1.1a.2 and 5.6.1.2.b are met. A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core locations.

CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 48 full length control rod assemblies. The full length control rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values of absorber material shall be 80 percent silver, 15 percent indium and 5 percent cadmium. All control rods shall be clad with stainless steel tubing.

5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:

a. In accordance with the code requirements specified in Section 5.2 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements,

b. For a pressure of 2485 psig, and

c. For a temperature of 6501F, except for the pressurizer which is 6801F.

VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 9914 +/- 100 cubic feet at an indicated Tavg of 587.41F.

5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.

SUMMER - UNIT 1 5-6 Amendment No. 27-1-554-62, 74, 105, 116, 119, 160

DESIGN FEATURES 5.6 FUEL STORAGE CRITICALITY 5.6.1.1 The spent fuel storage racks consist of 1712 individual storage cells. The cells are grouped into two regions, which are determined based on storage cell spacing as defined Ke, less below. The spent fuel storage racks are designed, and shall be maintained, with a than or equal to 0.95 when flooded with unborated water, which includes conservative for allowances for uncertainties and biases. This is ensured by maintaining the following each region:

a. REGION 1 - designated for storage of fresh fuel assemblies and fuel assemblies with a cumulative burnup less than the required cumulative burnup for storage in Region 2.

1. A nominal 10.867 inch center-to-center distance between fuel assemblies placed in the storage rack.

2. A maximum nominal initial enrichment of 4.95 weight percent U-235.

b. REGION 2 - designated for storage of discharged fuel assemblies.

1. A nominal 9.07 inch center-to-center distance between fuel assemblies placed in the storage rack.

2. A cumulative burnup with the acceptable domain defined by Figure 3.7-1.

5.6.1.2 The new fuel storage racks consist of 60 individual cells, each of which shall be accommodates a single assembly. The new fuel pit storage racks are designed and less 0.95 when flooded with unborated water and maintained with a Kf, less than or equal to than or equal to 0.98 for low density optimum moderation conditions, including conservative allowances for uncertainties and biases. This is ensured by maintaining:

a. A nominal 21 inch center-to-center distance between new fuel assemblies placed in the storage rack.

b. A nominal enrichment of 5.0 weight percent U-235.

DRAINAGE 5.6.2 The spent fuel pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 460'3".

CAPACITY capacity 5.6.3 The spent fuel pool is designed and shall be maintained with a storage Region 1 and 1512 limited to no more than 1712 fuel assemblies, with 200 assemblies in assemblies in Region 2.

5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT shall be maintained within 5.7.1 The components identified in Table 5.7-1 are designed and the cyclic or transient limits of Table 5.7-1.

SUMMER - UNIT 1 5-7 Amendment No. 27 74-,116, 444, 160

DESIGN FEATURES This page intentionally left blank.

5-8 Amendment No. 160 SUMMER UNIT 1

DESIGN FEATURES This page intentionally left blank.

Amendment No. 1 60 SUMMER UNIT 1 5-9