ML20070N144
| ML20070N144 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/22/1994 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070N147 | List: |
| References | |
| GL-91-08, GL-91-8, NUDOCS 9405050127 | |
| Download: ML20070N144 (37) | |
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UNITED STATES yq)fl[.4 5 i E
NUCLEAR REGULATORY COMMISSION E
WASHINGTON, D.C. 20556-0001 1
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VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE
- 4 i
DOCKET NO. 50-338 NORTH ANNA POWER STATION. UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 181 License No. NPF-4 1.
The Nuclear Regulatory Commission (the Commission) has found that:
l A.
The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated October 8,1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the i
Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common i
defense and security or to the health and safety of_ the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51
)
of the Commission's regulations and all applicable. requirements have been satisfied.
9405050127 940422 PDR ADOCK 05000338 p
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2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.D.(2) of Facility Operating License No. NPF-4 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.181, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days, F
HE NUCLEAR REGULATORY COMMISSION 1
i H bert N. Berko, Director Project Directorate 11-2 l
Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications i
Date of Issuance: April 22, 1994 r
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ATTACHMENT TO LICENSE AMENDMENT NO. 181 TO FACILITY OPERATING LICENSE N0. NPF-4 DOCKET N0. 50-338 Replace the follcwing pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
Remove Pages Insert Paaes IX IX 1-2 1-2 3/4 6-1 3/4 6-1 3/4 6-15 3/4 6-15 3/4 6-16 3/4 6-16 3/4 6-17 3/4 6-17 3/4 6-18 thru 3/4 6-32 B 3/4 6-3 8 3/4 6-3
i i
1 1
INQEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 9
1 SECTION I
EAGE i
4 3/4/a FI FCTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES Operating....................................................................................
3/4 8 1 Shutdown....................................................................................
3/48-5 3/4.82 ONSITE POWER DISTRIBUTION SYSTEMS A.C. DISTRIBUTION - Operating.......................................
3/486 A.C. and D.C. DISTRIBUTION - Shutdown................................
3/487 D.C. DISTRIBUTION - Operating.................................................
3/4 8-8 3/4.9 REFUEL ING OPERATIONS 3/4.9.1 BORON CONCENTRATION............................................
3/4 9 1 3/4.9.2 I NSTR UM ENTATION................................................................... 3/492 3/4.9.3 D ECAY H EAT.....................................................................
3/49-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS...........................
3/494 3/4.9.5 C OMM UNIC ATIONS....................................................................
3/4 9 5 3/4.9.6 MANIPULATOR CRANE OPERABILITY......................................
3/49-6 3/4.9.7 CRANE TRAVEL - SPENT FU EL PIT........................................
3/497 3/4.9.8 RESIDUAL HEAT REMOVAL (RHR) AND COOLANT CIRCULATION Normal Water Level......................................................................
3/4 9 6 Low Water Levels.....................................................................
3/4 9 4 a 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM. " 5499 3/4.9.10 WATER LEVEL-REACTOR VESSEL Fuel Assemblies...................................................................
3/4910 Contml Rods................................................................ 3/4-9 10s j
4 i
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NORTH ANNA - UNIT 1 IX Amendment No.32, 181 i
1
l INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE I
3/4.9.11 SPENT FUEL PIT WATER LEVEL.............................
3/4 9-11 4
3/4 9.12 FUEL BUILDING VENTILATION SYSTEM.......................
3/4 9-12 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN...........................'......,.......
3/4 10-1 3/4.10.2 GROUP HEIGHT INSERTION AND POWER DISTRIBUTION..........
3/4 10-2 3/4.10.3 PHYSICS TEST...........................................,,
3/4 10-3 3/4.10.4 REACTOR COOLANT L00PS..................................
3/4 10-4 c.
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4 NORTH ANNA - UNIT 1 X
Amendment No. 138,
1.0 DEFINITIONS The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications.
ACTION 1.1 ACTION shall be that part of a Specification which prescribes remedial measures required under designated conditions.
AXIAL FLUX DIFFERENCE 1.2 AXIAL FLUX DIFFERENCE shall be the difference in normalized flux signals, expressed in % of RATED THERMAL POWER between the top and bottom halves of a two section excore neutron detector.
CHANNEL CALIBRATION 1.3 A CHANNEL CALIBRATION shall be the adj ustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRA-TION shall encompass the entire channel including _the, sensor _and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST.
The CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.
CHANNEL CHECK 1.4 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation.
This determination shall include, where possible, comparison of the channel indication and/or status with other indica-tions and/or status derived from independent instrumentation channels measuring the same parameter.
CHANNEL FUNCTIONAL TEST 1.5 A CHANNEL WNCTIONAL TEST shall be:
- a. Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions.
- b. Bistable channels the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions.
CONTAINMENT INTEGRITY 1.6 CONTAINMENT INTEGRITY shall exist when:
1.6.1 All penetrations required to be closed during accident conditions are either:
I NORTH ANNA - UNIT 1 1-1 Amendment No. H,48
{
1.0 DEFINITIONS (Continued) l Capable of being closed by an OPERABLE containment automatic isolation valve a.
system, or b.
Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except for valves that are open under administrative control as permstted by Specsfication 3.6.3.1.
1.6.2 ' AN equipment hatches are closed and sealed.
1.6.3 Each air lock is OPERABLE pursuant to Specification 3.6.1.3.
r 1.6.4 The containment leakage rates are within the limits of Specification 3.6.1.2 ard 1.6.5 The sealing mecharusm assochsted with each penetration (e.g. welds, bellows or O. rings) is OPERABLE.
CONTROt.t ED LEAKAGE 1.7 CONTROLLED LEAKAGE shaN be that seal water flow supplied to the reactor coolant W@ HW.
CORE ALTERATION 1.8 CORE ALTERATION shall be the movement or manipuistion of any component within the reactor pressure vessel with the vessel head removed and fuelin the vessel. auspensen of CORE ALTERATION shall not preclude completion of movement of a cornponent to a safe conservative positen.
CORE OPERATING 1 lufTE REPORT 1.9 The CORE OPERATING LIMITS REPORT is the unit specific document that provides core operating limits for the current operating reload cycse. These cyc :.;.caic core operating limits shall be determined for each reload cycle in accordance with Specification 6.9.1. 7 Plant operation within these operating limits is addressed in individual specifications.
DOSE EOulvAt FNT l-131 1.10 The DOSE EQUIVALENT l-131 anaN be that concentration of I 131 (micsoaunes/ gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I 131, I-132,1-133,1 134 and 1-135 actually present. The thyroad dose conversen fadors used for this calculation shaN be those listed in Table 111 of TID-14844. Tak:utation of Distance Fadors for 1
Power and Test Reactor Sites".
5-AVERAGF DISINTEGRATION ENERGY 1.11 E shaN be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than iodines, with hall lives greater than 15 minutes, making up at least 95% of the total norpiodine activity in the coolant.
NORTH ANNA-UNIT 1 1-2 Amendments No. **. 'S, "=,181
1 3/4.6 CONTAINMENT SYSTEMS 3/4 6.1 CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION i
3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY:
MODES 1,2,3, and 4 ACTION Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
i At least once per 31 days by verifiying that all penetrations
- not capable of being a.
closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or 4
deactivated automatic valves, secured in their positions, except for valves that are open under administrative control as permitted by Specification 3.6.3.1.
b.
By verifying that each containment air lock is OPERABLE per Specification 3.6.1.3.
After each closing of the equipment hatch, by leak rate te_ sting the equipment c.
hatch seals, with gas at Pa, greater than or equal to 44.1 psig, and venfying that when the measured leakage rate for these seals is added to the leakage rates determined pursuant to Specification 4.6.1.2.b for all other Type B and C l
penetrations, the combined leakage rate is less than orequal to 0.60 La.
d.
Each time containment integrity is established after vacuum has been broken by pressure testing the butterfly isolation valves in the containment purge lines and the containment vacuum ejector line.
- Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked sealed or otherwise sealed in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that such surveillance need not be performed more often than once per 92 days.
NORTH ANNA-UNIT 1 3/4 6-1 Amendment No.446, KL3.. I 81
i CONTAINMENT SYSTEMS i
3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION i
3.6.3.1 Each containment isolation valve shall be OPERABLE.*
l APPLICABILITY:
MODES 1,2,3, and 4.
1 ACTION:
j With one or more of the isolation valves inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and:
Restore the inoperable valve (s) to OPERABLE status within 4 a.
j hours, or 1
~
b.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or g
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Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least c.
one closed manual valve or blind flange; or 3
d.
Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD q
SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
The provisions of Specification 3.0.4 do not apply.
l i
SURVEILLANCE REQUIREMENTS j
i 4.6.3.1.1 Each containment isolation valve shall be demonstrated I
i OPERABLE:
j a.
i At least once per 92 days by cycling each weight or spring loaded check valve testable during plant operation, through one complete i
cycle of full travel and verifying that each check valve remains closed when the differential pressure in the direction of flow is less than 1.2 psid and opens when the differential pressure in the direction of flow is greater than or equal to 1.2 paid but less than 5.0 3
paid.
i i
- Locked or sealed closed valves may be opened on an intermittent basis under administrative control.
NORTH ANNA UNIT-1 3/4 6-15 Amendment No.181 4
4 1
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d CONTAINMENT SYSTEMS
)
l SURVEILLANCE REQUIREMENTS (Continued) 4 1
b.
Prior to retuming the valve to service after maintenance, repair or replacement work is performed on the valve or its associated 1
actuator, control or power circuit by performance of the applicable
]
cycling test and verification of isolation time.
l t
4.6.3.1.2 Each containment isolation valve shall be demonstrated i
OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:
.L Verifying that on a Phase A containment isolation test signal, each a.
Phase A isolation valve actuates to its isolation position.
1 b.
Verifying that on a Phase B containment isolation test signal, each 4
Phase B isolation valve actuates to its isolation position.
Verifying that on a Containment Purge and Exhaust isolation signal, j
c.
each Purge and Exhaust valve actuates to its isolation position.
i d.
Cycling each weight or spring loaded check valve not testable during plant operation, through one complete cycle of full travel and verifying that each check valve remains closed when the differential 4
pressure in the direction of flow is less than 1.2 psid and opens when the differential pressure in the direction of flow is greate'r than or equal to 1.2 psid but less than 5.0 psid.
4.6.3.1.3 The isolation time of each power operated or automatic containment isolation valve shall be determined to be within its limit when tested l
pursuant to Speerfication 4.0.5.
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1 NORTH ANNA - UNIT 1 3/4 6-16 Amendment No. a,181 t
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PAGES 3/4 6-17 THROUGH 3/4 6-32 HAVE BEEN DELETED i
9 NORTH ANNA - UNIT 1 3/4 6-17 Amendment No.90,181 i
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CONTAINMENT SYSTEMS BASES 3/4.8.2.3 CHEMICAL ADDITION SYSTEM The OPERABILITY of the chemical addition system ensures that sufficient NaOH is added to the containment spray in the event of a LOCA. The limits on
' NaOH minimum volume and concentration, ensure that 1) the lodine removal efficiency of the spray water is maintained because of the increase in pH value, and 2) corrosion effects on components within containment are minimized. The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics. These assumptions are consistent with the iodine removal efficiency assumed in the accident analysis.
3/4.8.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment. Containment isolation within the times limits specified ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.
The opening of locked or sealed closed containment isolation valves on an intermittent basis under administrative control includes the following considerations: (1) stationing an operator, who is in communication with control room, at the valve controls, (2) instructing this operator to close the valve (s) in an accident situation, and (3) assuring that environmental conditions will not preclude access to close the valve (s) and that this action will prevent the release of radioactivity outside the containment.
3/4.8.4 COMBUSTlBLE GAS CONTROL The OPERABILITY of the equipment and systems required for the detection and control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below its fiammable limit during post LOCA conditions. Either recombiner unit.is capable of controlling the expected hydrogen generation associated with 1) zirconium-water reactions,2) radiolytic decomposition of water 3) corrosion of metals within containment. These hydrogen control systems are consistent with the recommendations of Regulatory Guide 1.7, " Control of Combustible Gas Concentrations in Containment Following a LOCA", March 1971.
NORTH ANNA - UNIT 1 8 3/4 6 3 Amendment No.181
~
_g CONTAINMENT SYSTEMS BASES 3/4.6.5 SUBATMOSr;;ERIC PRESSURE CONTROL SYSTEM 3/4.6.5.1 STEAM JET AIR EJECTOR ine closure of the isolation valves in the suction of the steam jet air ejector-ensures that 1) the containment internal pressure may be maintained within its operation limits by,the mechanical vacuum pumps and 2) the containment atmosphere is isolated from the outside environment in the event of a LOCA. These valves are required to be closed for containment intergrity.
NORTH ANNA - UNIT 1 B 3/4 6-4
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pa ncy fi NL UNITED STATES f
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.j NUCLEAR REGULATORY COMMISSION
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WASHINGTON. D.C. 20555-0001
%, +... 4s VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC C00 PERATIVE DOCKET NO. 50-339 NORTH ANNA POWER STATION. UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 162 License No. NPF-7 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company et al., (the licensee) dated October 8,1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as i
amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; i
B.
The facility will operate in conformity with the application, the i
provisions of the Act, and the rules and regulations of-the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be i
conducted in compliance with the Commission's regulations; i
D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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3 l 2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-7 is hereby amended to read as follows:
(2) Technical Soecifications j
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 162, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
l 3.
This license amendment is effective as of its date of issuance and shall 1
l be implemented within 30 days.
FOR T E NUCLEAR REGULATORY COMMISSION l
H bert N. Berkow, Director P oject Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation i
Attachment:
Changes to the Technical l
Specifications Date of Issuance: April 22, 1994 l
ATTACHMENT TO LICENSE AMENDMENT NO. 162 TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET N0. 50-339 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated..The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
Remove Paaes Insert Paaes VIII VIII IX IX l-2 1-2 3/4 6-1 3/4 6-1 3/4 6-14 3/4 6-14 3/4 6-15 3/4 6-15 3/4 6-16 3/4 6-16 3/4 6-17 thru 3/4 6-31 3/4 8-16 3/4 8-16 3/4 8-18 3/4 8-18' W
3/4 8-19 and 3/4 8-20 3/4 8-21 3/4 8-21 3/4 8-22 3/4 8-22 l
3/4 8-23 thru 3/4 8-25 i.
3/4 8-26 3/4 8-26 3/4 8-27 3/4 8-27 l
B 3/4 6-3 B 3/4 6-3 4
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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 S a f e ty V a l v e s..........................................
3 / 4 7-1 Aux i l i a ry Feedwa + er Sys tem.............................
3/4 7-5 Emergency Condensate Storage Tank......................
3/4 7-7 Activity...............................................
3/4 7-8 Main Steam Trip Valves.................................
3/4 7-10 Steam Turbine Assembly.................................
3/4 7-11 Ove rs peed P ro tec ti on................"...................
3/4 7-12 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION........
3/4 7-13 3/4.7.3 COMPONENT COOLING WATER SUBSYSTEM......................
3/4 7-14 3/4.7.4 SERVICE WATER SYSTEM...................................
3/4 7-15
~
3/4.7.5 ULTIMATE HEAT SINK.....................................
3/4 7-16 3/4.7.6 FLOOD PROTECTION.......................................
3/4 7-17 3/4.7.7 CONTROL ROOM EMERGENCY HABITABILITY SYSTEMS............
3/4 7-18 3/4.7.8 SAFEGUARDS AREA VENTILATION SYSTEM.....................
3/4 7-21 3/4.7.9 RESIDUAL HEAT REMOVAL SYSTEM RHR - Ope ra ti n g........................................
3/ 4 7-2 3 RHR - Shutdown.........................................
3/4 7-24 3/4.7.10 SNUBBERS...............................................
3/4 7-25 3/4.7.11 SEALED SOURCE CONTAMINATION............................
3/4 7-51 3/4.7.12 SETTLEMENT OF CLASS 1 STRUCTURES.......................
3/4 7-53 3/4.7.13 GROUNDWATER LEVEL-SERVICE WATER RESERV0IR..............
3/4 7-57 NORTH ANNA - UNIT 2 VII l
l l
lliD.EX
.........UMmNG CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS M
PAGE 3/4.8 FI FCTRICAL POWER SYSTEMS 3/4.8.1 A. C. SOURCES Operatin0............................................................................
3/481 Shutdown.........................................................................
3/4 8-10 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A. C. Distsbution - Operating.................................
3/4 8-11 A. C. and D.C. Distrbution Shutdown.................................
3/4 8-12 D. C. Distrbution - Operating..................................................
3/4813 Containment Penetration Conductor Overwrrent Protective Devcas......................................................
3/4 8-16 Motor Operated Vahes Thermal Overload Protection Devces...................................................
3/4 8-21 NORTH ANNA-UNIT 2 Vill Amendmett No.35,.uta, M2
l IUDEE 4-LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS f
f SECTION EAGE J
3/4 9 REFUFl ING OPERATIONS I
3/4.9.1 BORON CONC ENTRATION....................................................
3/4 9-1 j
3/4.9.2 I NSTR U M ENTATI ON..............................................................
3/4 9 2 j
3/4.9.3 DECAYTIME..............................................................................
3/493 i
3/4.9.4 CONTAINMENT BUILDING PENETRATIONS......................
3/4 9 4 3/4.9.5 COM M UN I CATI ONS............................................
3/49-6 3/4.9.8 M ANIPULATOR CRAN E OPERABILITY.....................................
3/4 9 7 3/4.9.7 CRANE TRAVEL - SPENT FUEL PIT..................................
3/4 9-8 3/4.9.8 RESIDUAL HEAT REMOVAL (RHR) AND COOLANT CIRCULATION Normal Water Level................................................
3/4 9 9 Low Water Levels...................................................
3/4 9 9a 3rd.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM 3/4910 3/4.9.10 WATER LEVEL - REACTOR VESSEL Fuel Assemblies....................................................................
3/4911 Control Rods..........................................................................
3/4 911a 3/4.9.11 SPENT FUEL PIT WATER LEVEL..................
3/4912 3/4.9.12 FUEL BUILDING VENTILATION SYSTEM..............................
3/4913 3/4 10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SH UTDOWN M ARGIN.....................................................
3/410-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION...
3/4 10-2 3/4.10.3 PHYSIC S TEST......................................................................... 3/410-3 3/4.10.4 REACTOR COOLANT LOOPS..............................-................
3/4 10-4 1
1 NORTH ANNA-UNIT 2 IX Amendment No.@,162 1
j INDEX UMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS 4
4 SECTION E22 3/4.11 RADIOACTIVE STORAGE 3/4.11.1 UQUID STORAGE l
Liquid Holdup Tanks..
3/4 11 2
)
in 3/4.11.2 GASSTORAGE E xplo siv e G a s Mixtu re.............................................
3/4 11-4 l
Gas Storage Tanks...............
3/4 11-5 i
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1 i
4 4
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1 1
i 1
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4 NORTH ANNA-UNIT 2 X
Amendment No. 37,114,
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1.0 DEFINITIONS e
u The defined terms of this section appear in capitalized type and are i
applicable throughout these Technical Specifications.
ACTION 1.1 ACTION shall be that part of a Specification which prescribes remedial g
measures required under designated conditions.
AXIAL FLUX DIFFERENCE i
,o
~
i 1.2 AXIAL FLUX DIFFERENCE shall be the difference in normalized flux signals, expressed in % of RATED THERMAL POWER bstween the top and bottom halves of a two section excore neutron detector.
CHANNEL CALIBRATION 1.3 A CHANNEL CALIBRATION shall be the adjustment, as necessary..- of the i
channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The. CHANNEL CALIBRA-l TION shall encompass the entire channel including the sensor and alarm and/or j
trip functions, and shall include the CHANNEL FUNCTIONAL TEST.
The CHANNEL j
CALIBRATION may be performed by any series of, sequential, overlapping or total
]
channel steps such that the entire-channel is calibrated; '
i, CHANNEL CHECK
- 1 1.4 A CHANNEL CHECK shall be the qualitative assessment of channel behavior q
during operation by observation.
This determination shall include, where possible, comparison of the channel indication and/or status with other indica-j tions and/or status derived from independent instrumentation char.nels measuring I
{
the same parameter.
CHANNEL FUNCTIONAL TEST 4
j i
1.5 A CHANNEL FUNCTIONAL TEST shall be:
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- a. Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including
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alarm and/or trip functions.
i the injection of a simulated' signal into the i
- b. Bistable channels sensor to verify OPERABILITY including alarm and/or trip functions.
CONTAINMENT INTEGRITY l
1.6 CONTAINMENT INTEGRITY shall exist when:
j 1.6.1 All penetrations required to be closed during accident conditions are either:
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NORTH ANNA - UNIT 2 1-1 Amendment No. 3y j
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4 1.0 DEFINITIONS (Continued)
Capable of being closed by an OPERABLE containment automatic isolation valve a.
system, or b.
Closed by manual valves, blind flanges, or deactivated automatic valves secured I
in their closed positions, except for valves that are open under administrative control as permitted by Specification 3.6.3.1.
1.6.2 All equipment hatches are closed and sealed.
1.6.3 Each air lock is OPERABLE pursuant to SpecNication 3.6.1.3.
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1.6.4 The containment leakage rates are within the limits of Specification 3.6.1.2 and i
1.6.5 The sealing mecharusm associated with each penetration (e.g. welds, bellows or 0 rings) i is OPERABLE.
t CONTROL i Ft3 t_EAKAGF I
1.7 CONTROLLED LEAKAGE shall be that seal water flow supphed to the reador molant pump seals.
j CORE ALTERATION 4
I 1.8 CORE ALTERATION shall be the movement or manipulation of any component within the reactor pressure vessel with the vessel head removed and fuel in the vessel. suspension of CORE ALTERATION shall not preclude completion of movement of a corgonent to a safe I
conservative position 1
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CORE OPERATING t tulTS REPORT 1
2, 1.9 The CORE OPERATING LIMITS REPORT is the unit specific document that provides j
core operating limits for the current operating reload cycle. These cyC Wic core operating limits shau be determined for each reload cycle in accordance with Specification 6.9.1.7 Plant operation within these operating limits is addressed in indmdual specifications.
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D_OSE EOtllVAl FNT l.131 1.10 The DOSE EQUIVALENT b131 shall be that concentration of I 131 (microcunes/ gram) whch alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, l-132,1 133, l-134 and 1 135 actuany presort. The thyrood does conversion factors used for this calculation shah be those listed in Table 111 of TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites".
~E-AVERAGF DISINTEGRATION ENERGY 1.11 E shall be me average (weighted in proporbon to the concentration of each radionuchde in the reactor coolant at the time of sampling) of the sum of the average beta and gamma
. energies per disintegration (in MeV) for taotopes, other than iodmes, with half Eves greater than j
15 minutes, making up at least 95% of the total norHodme activity in the COoiant.
1 NORTH ANNA -UNIT 2 1-2 Amendments No.q,162
3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY:
MODES 1,2,3, and 4 ACTION Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREt 'ENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
i a.
At least once per 31 days by verifiying that all penetrations
- not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves, secured in their positions, except for valves that are open under administrative control as permitted by Specification 3.6.3.1.
b.
By venfying that each containment air lock is OPERABLE per Specification 3.6.1.3.
c.
After each closing of the equipment hatch, by leak rate testing the equipment hatch seals, with gas at Pa, greater than or equal to 44.1'psig, and venfying that when the measured leakage rate for these seals is added to the leakage rates determined pursuant to Specification 4.6.1.2.b for all other Type B and C penetrations, the combined leakage rate is less than orequal to 0.60 La.
d.
Each time containment integrity is established after vacuum has been broken by pressure testing the butterfly isolation valves in the containment purge lines and the containment vacuum ejector line.
- Except valves, blind flanges and deactivated automatic valves which are located inside the containment and are locked sealed or otherwise sealed in the closed position. These penetrations shall be venfied closed during each COLD SHUTDOWN except that such surveillance need not be performed more often than once per 92 days.
NORTH ANNA - UNIT 2 3/4 6-1 Amendment No.39, M+,162
CONTAINMENT SYSTEMS CHEMICAL ADDITION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.3 The chemical addition system shall be OPERABLE with:
a.
A chemical addition tank containing a volume of between 4800 and 5500 gallons of between 12 and 13 percent by weight NaOH solution, and b.
A chemical addition flow path capable of adding NaOH solution from the chemical addition tank to both containment quench spray system pumps via the RWST.
APPLICiBILITY:
MODES 1, 2, 3 and 4.
ACTION:
With the chemical addition system inoperable, restore the~ system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANOBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the chemical addition system ts OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS I
wL.
44 4.6.2.3 The chemical addition system shall be demonstrated OPERABLE:
a.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed or otherwise secured in position, is in its correct position.
b.
At least once per 6 months by:
1.
Verifying the contained solution volume in the tank, and 2.
Verifying the concentration of the Na0H solution by chemical analysis.
c.
At least once per 18 months, during shutdown, by verifying that each automatic valve in the flow path actuates to its correct position on a Containment Pressure -- high-high test signal.
d.
At least once per 5 years by verifying individual flow from the RWST and the chemical addition tank thru the drain lines in the cross connection between the respective tanks.
NORTH ANNA - UNIT 2 3/4 6-13
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CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3.1 Each containment isolation valve shall be OPERABLE.*
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APPLICABILITY:
MODES 1,2,3, and 4.
ACTION:
With one or more of the isolation valves inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and:
Restore the inoperable valve (s) to OPERABLE status within 4 a.
hours, or b.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least c.
one closed manual valve or blind flange; or d.
Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
The provisions of Specification 3.0.4 do not apply.
l SURVEILLANCE REQUIREMENTS 4.6.3.1.1 Each containment isolation valve shall be demonstrated OPERABLE:
At least once per 92 days by cycling each weight or spring loaded a.
check valve testable during plant operation, through one complete cycle of full travel and verifying that each check valve remains closed when the differential pressure in the direction of flow is less than 1.2 psid and opent. when the differential pressure in the direction of flow is greater than or equal to 1.2 paid but less than 5.0 psid.
b.
Prior to retuming the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by performance of the applicable cycling test and verification of isolation time.
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- Locked or sealed closed valves may be opened on an intermittent basis under administrative control.
NORTH ANNA UNIT-2 3/4 6-14 Amendment No.162
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J CONTAINMENT SYSTEMS I
SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.1.2 Each containment isolation valve shall be demonstrated 1
OPERABLE during the COLD GHUTDOWN or REFUELING MODE at least once i
per 18 months by:
)
)
Verifying that on a Phase A containment isolation test siCnal, each a.
j Phase A isolation valve actuates to its isolation position.
b.
Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve actuates to its isolation position.
i c.
Verifying that on a Containment Purge and Exhaust isolation signal, each Purge and Exhaust valve actuates to its isolation position.
J d.
Cycling each weight or spring loaded check valve not testable during plant operation, through one complete cycle of full travel and
}
verifying that each check valve remains closed when the differential j
pressure in the direction of flow is less than 1.2 psid and opens i
when the differential pressure in the direction of flow is greater than j
or equal to 1.2 psid but less than 5.0 psid. --
4.6.3.1.3 The isolation time of each power operated or automatic containment isolation valve shall be determined to be within its limit when tested
)
j pursuant to Specification 4.0.5.
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NORTH ANNA - UNIT 2 3/4 6-15 Amendment No.162 7
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ELECTRICAL POWER SYSTEMS 0.C.
DISTRIBUTION - SHUTDOWN LIMITING CONDITION FOR OPERATION
'3.8.2.4 As a minimum, the following D.C. electrical equipment and bus shall be energized and OPERABLE:
2 125-volt D.C. busses, 2-I or 2-III and 2-II or 2-IV 2 125-volt battery bank and charger associated with the above D.C. busses.
APPLICABILITY:
MODES 5 and 6.
ACTION:
With less than the above complement of D.C. equipment and bus OPERA 8LE, establish CONTAINMENT INTECRITY within 8 Hours.
SURVEILLANCE REQUIREMENTS 4.8.2.4.1 The above required 125-volt D.C. bus shall be determined OPERABLE and energized at least once per 7 days by verifying correct breaker alignment and indicated power availability.
4.8.2.4.2 The above required 125-volt battery bank and charger shall be demonstrated OPERABLE per Surveillance Requirement 4.8.2.3.2.
NORTH ANNA - UNIT 2 3/4 8-15
ELECTRICAL POWER SYSTEMS CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES LIMITING CONDITION FOR OPERATION 3.8.2.5 Primary and backup containment penetration conductor overcurrent protective devices associated with each containment electrical penetration circuit shall be OPERABLE. The scope of these protective devices excludes those circuits for which creditable fault currents would not exceed the electrical penetration design rating.
APPLICABILITY-MODES 1,2,3 and 4.
ACTION:
With one or more of the containment penetration conductor overcurrent protective device (s) inoperable either:-
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Restore the protective device (s) to OPERABLE status orde '
a.
energize the circuit (s) by tripping the associated circuit breaker ~
7-vithin 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and verify the circuit breaker to be tripped at least once per 7 days thereafter; the provisions of Spec,;fn 4;on 3.0.4 are
)
t not applicable to overcurrent devices in circuits which have their circuit breakers tripped, or b.
Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.8.2.5 All containment penetration conductor overcurrent protective devices shall be demonstrated OPERABLE:
a.
At least once per 18 months:
1.
By verifying that, on a rotating basis at least one 4.16 KV circuit breaker is OPERABLE by performing the following:
(a)
A CHANNEL CALIBRATION of the associated protective relays, and (b)
An intergrated system functional test which includes simulating automatic actuation of the system and verifying that each relay and associated circuit brsakers and control circuits function as designed.
l NORTH ANNA - UNIT 2 3/4 8-16 Amendment No.162 e
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i ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 2.
By verifying the OPERABILITY of molded case circuit breakers, 3
by selecting and functionally testing a representative sample of at least 10% of all the circuit breakers of that type.
i Circuit breakers selected for functional testing shall be i
selected on a rotating basis.
The functional test shall consist l
of injecting a current input at the specified setpoint to each selected circuit breaker and verifying that each circuit breaker 3
functions as designed.
Circuit breakers found inoperable
)
during functional testing shall be restored to OPERABLE status prior to resuming operation.
For each circuit breaker found inoperable during these functional tests, an additional repre-sentative sample of at least 10% of all the circuit breakers of the inoperable type shall also be functonally tested until no j
i more failures are found or all circuit breakers of that type j
have been functionally tested.
4 3.
By verifying the OPERABILITY of fuses, by selecting ana runction-j ally testing a representative sample of each typc of fuse on a rotating basis.
Each representative sample c7 fuses shall include at least.10% of all fuses 'of that type.
The functional j
test shall consist of a non-destructive resistance measurement i
j test which demonstrates that the fuse meets its manufacturer's design criteria.
Fuses found inoperable during these functional i
tests shall be replaced with OPERABLE fuses prior to resuming operation.
For each fuse found inoperable during these func-3 tional tests, an additional representative sample of at least l
10% of all fuses of that type shall be functionally tested j
until no more failures are found or all fuses of that type have
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]
been functionally tested.
b.
At least once per 60 months by subjecting each circuit breaker to an i
j inspection and preventive maintenance in accordance with procedures j
j prepared in conjunction with its manufacturer's recommendations.
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i NORTH ANNA - UNIT 2 3/4 8-17
i PAGES 3/4 8-19 and 3/4 8 AVE BEEN DELETED H
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NORTH ANNA - UNIT 2 3/4 8-18 Amendment No.444,162
ELECTRICAL POWER SYSTEMS MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION DEVICES I
LIMITING CONDITION FOR OPERATION 3.8.2.6 The thermal overload protection devices, integral with the motor starter, of each valve used in safety systems shall be OPERABLE.
APPLICABILITY:
Whenever the motor operated valve is required to be OPERABLE.
ACTION:
With one or more of the thermal overload protection devices inoperable, declare i
the affected valve (s) ir operable and apply the appropriate ACTION Statement (s) for the affected valve (s).
SURVEILLANCE REQUIREMENTS 3
4.8.2.6 The above required thermal overload protection devices shall be demonstrated OPERABLE at least once per 18 months by the performance of a CHANNEL CAllBRATION of a representative sample of at least 25% of all thermal overload devices, such that each device is calibrated at least once per 6 years.
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NORTH ANNA - UNIT 2 3/4 6-21 Amendment No.162
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1 NORTH ANNA - UNIT 2 3/4 8-22 Amendment No. 74,162 r
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ELFCTRICAL POWER SYSTEMS
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NORMALLY DE-ENERGI7FD POWER CIRCUITS LIMITING CONDITION FOR OPERATION 3.8.2.7 All circuits that have containment penetrations and are not required during reactor operation shall be de-energized.
APPLICABILITY:
MODES 1,2,3,4.
ACTION:
With one or more of the circuits described above energized, de-energize the circuit (s) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.8.2.7 At least once per 31 days, verify that all the circuits described above are de-energized by noting the position of the appropriate circuit breakers.
NORTH ANNA-UNIT 2 3/4 8-26 Arnendrnent No.44,162
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4 NORTH ANNA - UNIT 2 3/4 8-27 h%nt No. 34,162
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CONTAINMENT SYSTEMS BASES i
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3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.1 and 3/4.6.2.2 CONTAINMENT QUENCH AND REClRCULATION SPRAY SYSit-MS The OPERABILITY of the containment spray systems ensures that containment depressurization and subsequent retum to subatmospheric pressure will occurin the event of a LOCA. The pressure reduction and resultant terminction of containment leakage are consistent with the assumptions used in j
the accident analyses.
3/4.8.2.3 CHEMICAL ADDITION SYSTEM i
The OPERABILITY of the chemical addition system ensures that sufficient NaOH is added to the containment spray in the event of a LOCA. The limits on NaOH minimum volume and concentration, ensure that 1) the iodine removal efficiency of the spray water is maintained because of the increase in pH value, and 2) corrosion effects on components within containment are minimized. The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics. These assumptions are consistent with the iodine removal efficiency assumed in the accident analysis.
3/4.8.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive materialto the containment atmosphere or pressurization of the containment. Containment isolation within the times limits specified ensures that the release of radioactive material to the environment will be consistent with the assumptions used in ther analyses for a LOCA.
The opening of locked or sealed closed containment isolation valves on an intermittent basis under administrative control includes the following..
considerations: (1) stationing an operator, who is in communication with control room, at the valve controls, (2) instructing this operator to close the valve (s) in an accident situation, and (3) assuring that environmental conditions will not preclude access to close the valve (s) and that this action will prevent the release of radioactivity outside the containment.
4 NORTH ANNA - UNIT 2 8 3/4 6-3 Amendment No.162
CONTAINMENT SYSTEMS BASES 3/4.6.4 COMBUSTIBLE GAS CONTROL The OPERABILITY of the equipment and systems required for the detection and control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions.
Either recombiner unit is capable of controlling the expected hydrogen generation associated with 1) zirconium-water reactions', 2) radiolytic decomposition of water 3) corrosion of metals within containment.
These hydrogen control systems are consistent with the recommendations of Regulatory Guide 1.7, " Control of Combustible Gas Concen-trations in Containment Following a LOCA", March 1971.
3/4.6.5 $UBATMOSPHERIC PRESSURE CONTROL SYSTEM 3/4.6.5.1 STEAM JET AIR EJECTOR The closure of the isolation valves in the suction of the steam jet air ejector ensures that 1) the containment internal pressure may be maintained within its operation limits by the mechanical vacuum pumps and 2) the containment atmosphere is isolated from the outside environment in the event of a LOCA.
These valves are required to be closed for containment intergrity.
NORTH ANNA - UNIT 2 B 3/4 6-4