ML20081J503

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Proposed TS 3.9.4 Re Containment Airlock Doors to Be Open During Fuel Movement
ML20081J503
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 03/17/1995
From:
GEORGIA POWER CO.
To:
Shared Package
ML20081J498 List:
References
NUDOCS 9503270315
Download: ML20081J503 (11)
v • d • e


Text

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ENCLOSURE 3 VOGTLE ELECTRIC GENERATING PLANT REQUEST TO REVISE TECHNICAL SPECIFICATIONS ALLOW CONTAINMENT AIRLOCK DOORS TO BE OPEN DURING FUEL MOVEMENT INSTRUCTIONS FOR INCORPORATION l

The proposed change to the Vogtle Electric Generating Plant Technical Specifications i would be incorporated as follows. l l

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4 Remove Page Insert Page 3/4 9-4 new 3/4 9-4 B 3/4 9-1 new B 3/4 9-1  :

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l REFtJELINbOPERATIONS 3/4'. 9. 4 CONTAINMENT BUILDING PENETRATIONS LIMITING CONDITION FOR OPERATION -

3.9.4 The containment building penetrations shall be in the following status:

a. The equipment door closed and held in place by a minimum of four bolts, '
b. A-m4*1 mum--af_nna 4ae in mach-air-loct S chsed,*end 216d[ b
c. Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either:
1) Closed by an isolation valve, blind flange, or manual valve, or  !
2) Be capable of being closed by an OPERABLE ~ automatic containment i ventilation isolation valve (HV-2626 A&B, HV-2627 A&B, HV-2628 A&B, HV-2629 A&B).

A_PPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within -

the containment.

ACTION: i

'l With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment building.

SURVEILLANCE REQUIREMENTS (refuinL 4.9.4 Each of the above required containment building penetrations shall be 4

determined to be either in its ch:;d,'i::ht;d condition or capable of being ,

closed by an OPERABLE automatic containment ventilation isolation valve (HV-2626 A&B, HV-2627 A&B, HV-2628 A&B, HV-2629 A&B) within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONS or movement of irradiated fuel in the containment building by: .

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a. Verifying the penetrations are in their c h x d/ M :ted condition, l or I
b. Testing the containment ventilation isolation valves per the applicable  ;

portions of Specification 4.6.3.2.

V0GTLE UNITS - 1 & 2 3/4 9-4 1

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INSERT A l I
b. The emergency airlock is isolated by at least one airlock door, and the j personnel airlock is isolable by at least one airlock door with a l designated individual available to close the personnel airlock door; and, ,

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3/4.9.. REFliELING OPERATIONS l

BASES j 3/4.9.1 BORON CONCENTRATION The limitations on reactivity conditions during REFUELING ensure that:

(1) the reactor will remain subcritical during CORE ALTERATIONS, and (2) a uniform boron concentration is maintained for reactivity control in the water ,

1 volume having direct access to the reactor vessel. The locking closed of the '

required valves, except valves 1208-U4-176 and 1208-U4-177 for short periods ,

of time to maintain chemistry control, during refueling operations precludes the possibility of uncontrolled boron dilution of the filled portions of the l Reactor Coolant System. These actions prevent flow to the RCS of unborated t water in excess of that analyzed. These limitations are consistent with the [

initial conditions assumed for the Boron Dilution Accident in the safety  ;

analysis. The Boron concentration value of 2000 ppm or greater ensures a K,ff of 0.95 or less and includes a conservative allowance for calculational .

uncertainties of 100 ppm of boron.

3/4.9.2 INSTRUMENTATION t

The OPERABILITY of the Source Range Neutron Flux Monitors ensures that i redundant monitoring capability is available to detect changes in the reactivity condition of the core.

3/4.9.3 DECAY TIME The minimum requirement for reactor suberiticality prior to movement of irradiated fuel assemblies in the reactor vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short-lived fission products. This decay time is consistent with the assumptions used in the  ;

safety analyses.

3/4.9.4 CONTAINMENT BUILDING PENETRATIONS [p The requirements on containment building enetration closure and OPERABILITY o  ;

ensure that a release of radioactive material wHMn containment will be mWNQ4T.

rect + ted h m la= bge to th; : M re ment. The OPERABILITY and closure ,

restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization  ;

potential while in the REFUELING MODE. Ic,,7 g [

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

V0GTLE UNITS - 1 & 2 B 3/4 9-1 Amendment No. 28 (Unit 1)

Amendment No. 9 (Unit 2)

INSERT B Item b of this LCO includes requirements for both the emergency airlock and the personnel airlock. The emergency airlock is required to be isolated by at least one airlock door at all times when Specification 3.9.4 is applicable.

The personnel airlock is required by Item b of this LCO to be isolable by at least one airlock door. Both containment personnel airlock doors may be open during movement ofirradiated fuel in the containment and during core alterations provided one airlock door is isolable. The personnel airlock is isolable when the following criteria are satisfied:

1. one personnel airlock door is OPERABLE,
2. at least 23 feet of water shall be maintained over the top of the reactor vessel flange in accordance with Specification 3.9.10.1,
3. a designated individual is available to close the door.

OPERABILITY of a containment personnel airlock door requires that the door seal protectors are easily removed, that no cables or hoses are being run through the airlock, and that the airlock door is capable of being quickly closed. The requirement that the plant maintain 23 feet of water above the reactor vessel flange ensures there is sufficient time to close the personnel airlock following a loss of shutdown cooling before boiling occurs. This requirement for the personnel airlock may be satisfied by maintaining at least one airlock door closed.

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. INDEX DEFINITIONS -

SECTION E8EE 1.0 DEFINITIONS  !

1.1 ACTI0N........................................................ 1-1 1.2 ACTUATION LOGIC TEST.......................................... 1-1 1.3 ANALOG CHANNEL OPERATIONAL TEST............................... 1-1 1.4 AXIAL FLUX DIFFERENCE......................................... 1-1 1.5 CHANNEL CALIBRATION........................................... 1-1 1.6 CHANNEL CHECK................................................. 1-1 ,

1.7 CONTAINMENT INTEGRITY......................................... 1-2 1.8 CONTROLLED LEAKAGE............................................ 1-2 ,

1.9 CORE ALTERATIONS.............................................. 1-2 1.10 CORE OPERATING LIMITS REP 0RT................................. 1-2  :

1.11 DOSE EQUIVALENT I-131........................................ 1-2 1.12 E-AVERAGE DISINTEGRATION ENERGY.............................. 1,73 ,

1.13 ENGINEERED SAFETY FEATURES RESPONSE TIME..................... 1-3 1.14 FREQUENCY N0TATION........................................... 1-3 1.15 GASEOUS WASTE PROCESSING SYSTEM.............................. 1-3 1.16 IDENTIFIED LEAKAGE........................................... 1-3 1.17 MASTER RELAY TEST............................................ 1-3 1.18 MEMBER OF THE PUBLIC......................................... 1-I 4 1.19 0FFSITE DOSE CALCULATION MANUAL.............................. 1-4 1.20 OPERABLE - OPERABILITY....... ............................... 1-4 l.21 OPERATIONAL MODE - M0DE...................................... 1-4 1.22 PHYSICS TESTS................................................ 1-4 1.23 PRESSURE BOUNDARY LEAKAGE.................................... 1-4 1.24 PROCESS CONTROL PR0 GRAM...................................... 1 -4 1.25 PURGE PURGING.............................................. 143' 7

l.26 QUADRANT POWER TILT RATI0.................................... 1-5 1.27 RATED THERMAL P0WER.......................................... 1-5 1.28 REACTOR TRIP SYSTEM RESPONSE TIME............................ 1-5 1.29 REPORTABLE EVENT.................... ........................ 1-5 1.30 SHUTOOWN MARGIN.............................................. 1-5 ,

i 1.31 SITE B00NDARY................................................ 1-5 i V0GTLE UNITS - 1 & 2 I Amendment No. 66 (Unit 1)

Amendment No. 45 (Unit 2) 2

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.. l DEFINITIONS j i

SECTION PAGE -

t 1.32 SLAVE RELAY TEST............................................. 1-5  :

1.33 SOLIDIFICATION (DELETED)..................................... 1-6 l l 1.34 SOURCE CHECK................................................. 1-6 1.35 STAGGERED TEST BASIS......................................... 1-6 .

1.36 THERMAL P0WER................................................ 1-6 1.37 TRIP ACTUATING DEVICE OPERATIONAL TEST....................... 1-6  !

1.38 UNIDENTIFIED LEAKAGE......................................... 1-6 1.39 UNRESTRICTED AREA............................................ 1-6 1.40 VENTILATION EXHAUST TREATMENT SYSTEM......................... 1-g 7 1.41 VENTING...................................................... 1-7  ;

1-8 I TABLE 1.1 FREQUENCY N0TATION......................................

TABLE 1.2 OPERATIONAL M0 DES....................................... 1-9 .

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I V0GTLE UNITS - 1 & 2 II Amendment No. 55 (Unit 1)

Amendment No. 34 (Unit 2)

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i LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Containment Integrity.................................... 3/4 6-1 Containment Leakage...................................... 3/4 6-2 Conta i nment Ai r Loc ks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 6-4 Internal Pressure........................................ 3/4 6-6 Air Temperature.......................................... 3/4 6-7 Containment Structural Integrity......................... 3/4 6-8 Containment Ventilation System........................... 3/4 6-11 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray System................................. 3/4 6-13 a

Spray Additive System.................................... 3/4 6-14 l

1 Containment Cooling System............................... 3/4 6-15 .

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i 3/4.6.3 CONTAINMENT ISOLATION VALVES............................. 3/4 6-16

. 3/4.6.4 COMBUSTIBLE GAS CONTROL Hydrogen Monitors........................................ 3/4 6-18 Electric Hydrogen Recombiners............................ 3/4 6-19 i

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V0GTLE UNITS - 1 & 2 IX

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IlWEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS ,

F SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Va1ves............................................ 3/4 7-1 TABLE 3.7-1 MAXIMUM ALLOWABLE POWER RANGE NEUTRON FLUX HIGH  !

SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES........ 3/4 7-2  !

TABLE 3.7-2 SiEAM LINE SAFETY VALVES PER L00P..................... 3/4 7-3 Auxi l iary Feedwater System. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7-4 L Condensate Storage Tank.................................. 3/4 7-6  ;

Specific Activity........................................ 3/4 7-7  !

TABLE 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE t AND ANALYSIS PR0 GRAM..................................... 3/4 7-8

_ Main Steam Line Isolation Va1ves......................... 3/4 7-9 3/4.7.2 ' STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.... ..... 3/4 7-10 3/4.7.3 COMPONENT COOLING WATER SYSTEM........................... 3/4 7-11 3/4.7.4 NUCLEAR SERVICE COOLING WATER (NSCW) SYSTEM. . . . . . . . . . . . . . 3/4 7-12 3/4.7.5 ULTIMATE HEAT SINK... ................................... 3/4 7-13 .

3/4 7-14 i 3/4.7.6 CONTROL ROOM EMERGENCY FILTRATION SYSTEM (Common System).

3/4.7.7 PIPING PENETRATION AREA FILTRATION AND EXHAUST SYSTEM.... 3/4 7-17

  • 3/4.7.6 SNUBBERS................................................. 3/4 7-19 FIGURE 4.7-1 SAMPLE PLAN 2 FOR SNUBBER FUNCTIONAL TEST............ 3/4 7-24

. TABLE 4.7-2 SNUBBER VISUAL INSPECTION INTERVAL..................... /4 7-24a l 3/4.7.9 SEALED SOURCE CONTAMINATION.............................. '/4 7-25 i3/4.7.10 AREA TEMPERATURE MONITORING.............................. 3/4 7-27  !

! TABLE 3.7-3 AREA TEMPERATURE MONITORING........................... 3/4 7-28 I3/4.7.11 ENGINEERED SAFETY FEATURES (ESF) ROOM COOLER AND SAFETY-RELATED CHILLER SYSTEM................................... 3/4 7-29 3/4.7.12 REACTOR COOLANT PUMP THERMAL BARRIER COOLING WATER  ;

IS0LATION................................................ 3/4 7-30 3/4.7.13 DIESEL GENERATOR BUILDING AND AUXILIARY FEEDWATER PUMPHOUSE ESF HVAC SYSTEMS .............................. 3/4 7-31

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V0GTLE UNITS - 1 & 2 X Amendment No. 41 (Unit 1)

Amendment No. 21 (Unit 2)

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    • INDEX l LIMITING CONDITIONS FOR OPERATION'AND SURVEILLANCE REQUIREMENTS ,

SECTION PAGE l

3/4.8 ELECTRICAL POWER SYSTEMS l

3/4.8.1 A.C. SOURCES ,

P Operating................................................ 3/4 8-1 TABLE 4.8-1 DIESEL GENERATOR TEST SCHEDULE........................ 3/4 8-9 Shutdown................................................. 3/4 8-10, ,

3/4.8.2 0.C. SOURCES 0perating.............................................. . 3/4 8-11 TABLE 4.8-2 3/4 8-13 BATTERYSURVEILLANCEREQUIREMENTS......V............

TA 8 At 9. B-3  ?"fo'*"'R D;5d*t' IEn 5 ###f'M# f f"' ~* 3/98*I3 R Shutdown................................................. 3/4 8-14 3/4.8.3 ONSITE POWER DISTRIBUTION 0perating................................................ 3/4 8-15 Shutdown................................................. 3/4 8-18 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Containment Penetration Conductor Overcurrent Protective Devices ano Feeder Breakers to Isolation Transformers Between 480 V Class 1E Busses and Non-Class 1E Equipment.............................................. 3/4 8-19 Safety-Related Motor-Operated. Valves Thermal Overload Protection and Bypass Devices.......................... 3/4 8-21 TABLE 3.8-1 SAFETY-RELATED MOTOR-0PERATED VALVES THERMAL OVERLOAD PROTECTION BYPASS DEVICES... ......... .............. . 3/4 8-22 V0GTLE UNITS - 1 & 2 XI

. INDEX ADMINISTRATIVE CONTROLS SECTION 6.4.2 SAFETY REVIEW BOARD (SRB)

Function.................................................. 6-9 Composition............................................... 6-10 Alternates................................................ 6-10 Consultants............................................... 6-10 Meeting Frequency......................................... 6-10 Quorum.................................................... 6-10 Review.................................................... 6-11 Audits.................................................... 6-11 Records................................................... 6-12 6.5 REPORTABLE EVENT ACTIQH..................................... 6-13 6.6 SAFETY LIMIT VIOLATION...................................... 6-13 6.7 PROCEDURES AND PR0 GRAMS..................................... 6-13 6.8 REPORTING REQUIREMENTS 6.8.1 ROUTINE REP 0RTS........................................... 6-17 Startup Report............................................ 6-17 Ann u a l Re p o r t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-17 Annual Radiological Environmental Surveillance Report..... 6-18 Annual Radioactive Ef fluent Release Report. . . . . . . . . . . . . . . . 6-19 l Monthly Operating Reports................................. 6-2/O Core Operating Limits Report ............................. 6-2fC 6.8.2 SPECIAL REP 0RTS........................................... 6-21/

6.9 RECORD RETENTION............................................ 6-22 V0GTLE UNITS - 1 & 2 XXIII Amendment No. 61 (Unit 1)

Amendment No. 40 (Unit 2)

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