ML20043B106
| ML20043B106 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/21/1990 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20043B104 | List: |
| References | |
| NUDOCS 9005240194 | |
| Download: ML20043B106 (73) | |
Text
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Attachment 1 i
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i Proposed Technical Specification Change - ).
North Anna Unit 1 !
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i Virginia Electric and Power Company I
i 9005240194 900521 '
INDEX EME SECTON 1.0 DEFINITIONS _ (continued) 15 R ated T he r m al Powe r . . . . . . .. . . . . . . . . . . . . . . . . . . .. .. . . . . . . . . . . . . . . . . . . . . . .. .. . . . . . . . . . . . .. . . . . . . .. .. . .... .. .. ..
- R e actor T rip Sy stem Response Time .......................... . ....... .......... ........ ............. 1 5 R epo rt able Ev e nt . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
S h u td ow n M a t gi n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . .
Sit e B o u n d a ry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
Sl av e R e l a y T e s t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
I SourceCheek...........................................................................................................1-5 St agg e r ed T e s t B a s i s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . .. . .
T h e r m al P o w e r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
U niden tili ed Le ak ag e . . . . . . .. .. . .. .. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . .. . . . . . . . . . . .
U n r e s t ric t e d Ar e a . . . . . . . . . . . . . . . . . . . . . .. . .. . . . . . . . . . . . . . . . . . . .. . . . . . .
Ventilation Exhaust Treatment System.... ................................ ............................. 1 6 Venting......................................................................................................16 la Amendment No.
NORTH ANNA-UNIT 1
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INDEX UMITING CONDITIONS FOR OPERATIOnl AND SURVEILLANCE REOUIREMENTS SECTION Ee2 3/4.2 POWER DISTRIBUTION LIMITS-3/4.2.1 A xla t Flu x Dif f e re nce . .. ...... . . . ........ . .. . .. . .. .. .. .. ... . ... ... . . ... . ... ... .. . ... .. . .... . . 3/4 21 3 / 4. 2. 2 Heat Flux Hot C hannel Factor................................................ ........ .. 3/4 25 7 3 / 4. 2. 3 Nuclear Enthalpy Hot Channel Factor................................................ 3/4 2-9 -
3 / 4 . 2 . 4 Ou ad rant Powe r Tilt R a11o .. .. .. ... ... . .. .. .. ... . .... .. .. . . . .. ...... .... ... . .. . . . . . .. .. ... . '3/4 2 12 3/4 2 14 4 3 / 4 . 2 . 5 D N B Pa ra m e t e rs .. .. . . . . .. .. . . . . .. .. .. . . .. . . . . .. .. .. . . . . .. . . .. . . .. . . . . .. . . . . .. . . .. . . . . . . . . . . . . . .
3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TR;P SYSTEM INSTRUMENTATION............. ............. ........ 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM -
I N ST R U M E N TAT l O N . . . . . . . . . . . . . . . . . . . . .. . . . . . . .. . . . . . . . . . . . . . . .. . . . . . .. . . . . . . . . . . .. .. . . . . . . 3/4 3 15 3/4.3.3 MONITORINGINSTRUMENTATION R a di at io n M o ni to rin g . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . .. . . . . 3/4 3 35 M ovable I nco re D e tectors .. . . .. .. ... .. .. .. .. .. .. .. .. .. .... .... .. .. .. .. . . . . . .. .. . .. .. .. . 3/4- 3 39 S els mic I n s tru m e nt atio n.............. .... ....... .... . .. ....... ..... .. .. . ..... .. ..... 3/4 3 40 M eteorological In strumentation... . .... ...... ...................................... 3/4 3 43 Auxiliary Shutdown Panel Monitoring instrumentation........... ........ 3/4 3 46 Accident Monitoring Instrumentation........... ............ ...... .......... ...... 3/4 3 49 Fire Detection instrumentation.............. ... .. ...... ....... .. .... .. .......... 3/4 3 52 Loose Parts Monitoring System... . . ......................... ........... .... ...... 3/4 3 56 Explosive Gas Monitoring Instrumentation.......... .............. . ........... 3/4 3 59 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION Startup and Power Operation.. .. . ... .... ............ ... .. ... . . . . . 3/4 4-1 Hot Standby...... ..... ....... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . 3/4 4-2 Shutdown........................................................................... 3/4 4-3 I so l a t e d Lo o p . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4
. 4-4 l s ol a te d Loop S t a rt u p. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-5 ;
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NORTH ANNA - UNIT 1 IV Amendment No. i l
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION Eeg l i
l 3/4.11 RADIOACTIVE STORAGE 3/4.11.1 UQUID STORAGE ;
Liq uid H old up Tanks......... ...................... ........... ...................... 3/4 11 2 :
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1 3/4.11.2- CASSTOR/GE E xp lo siv e G a s Mi x t u re . . .. . . . . . . . . . . . .. . . .. . . . .. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . 3/4 11-4 l 1
G a s S to r ag e Ta n ks . . . . . . . . . . .. . . .. . . . . . . . . . . . . . . . . . . . . . . . . . .. . .. . . . . .. . . . . . . .. . . . . . . ... . . . . . . 3/4 11 5 r
b NORTH ANNA - UNIT 1 XI Amendment No.
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3/4.11 RADIOACTIVE STORAGE j B 3/4 11-2 3/4.11.1 LI Q U I D S T O R AG E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . l 3/4.11.2 G A S S T O R AG E . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .B
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NORTH ANNA UNIT 1 XVil Amendment No.
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/ .r INDEX ADMINISTRATIVE CONTROLS SECTION ReE .I t
Consultants............................................................................................ 68 M e eting Fre q u e n cy.. . . .. . . .. . . .. . .. .. . . . . .. . . .. . . . . .. . .. . . . . . . . . .. . . .. . . . . . . . .. . . . . . . . . .. . .. . . .. . . 6-8' Review................................................................................................... 6-8 Authority............................................................................................... 6-9 Records.................................................................................................. 6-9' 6.5.3 QUAUTY ASSURANCE DEPARTMENT !
t Function................................................................................................. 10 Authority............................................................................................... 6 11 ,
Records................................................................................................. 6 11 6.6 R E PO R T AB LE E VE NT ACTION .. . . . . . . .. . . ... .. . .. . .. . .. . . . ... . . .. . . . ... . . . .. . . . .. . . . ... . . . . . . 6-12 6.7 S A F ETY LI M IT VI O LATI O N . . . .. . .. ... . . . . . . . . . . .. .. . .... . . . . .. . . . . ... . .. . . . . . . . .. . . . . . .. . . . . . . . 6 '1 2 6.8 P R OC E D U R E S AN D P R OG R AM S . .. ... . . . . . ... .. ... . . .. . . . ... ... .. . . .. . ... ... .. . . . . . .. . .. . .. . 6 12 6.9 REPORTING REQUIREMENTS . i 6.9.1 R O UT I N E R E P O RTS .. . . ... . . . . . . . . . .... . ... . . . . . . . . . .. .. . . . . . . . . .. .. . . .. .. . . .. . .. . . .. . . . . .. . . . . 6 14 6 . 9 . 2 S P E C I AL R E P O RTS .. . . . . . . .. . . . .. ... .. . . . . . . . .. . . .. .. . . . . .. . . . .. . . .. . . . . . . .. . . . .. . . . .. . . . . . . . .. . 6-21 6.10 R E C O R D R ET E NT10 N .. . . . . . . . . . . .. .. . . . .. .. . .. . . . .. . . .. . . . . .. . . . . . . . . . . . . .. . .. . .. . . . . . .. .6 . . . 22 6.11 RADI ATION PR OTECTI ON P ROG R AM............................................... .... 6 24 6.12 H I G H R A D I AT l ON A R EA . . . . . . .. . . . . .. . . . .. . . . . . . . . . . . . . . . . . ... .. .. . . . . . .. . .. .. . . . . . . . . . . 6-25 . . . . . ..
6.13' ENVIR ON M E NThL OUALI FI C ATIO N.............. ... .................................... 6-25'
' 6.14 P R OC ESS CONT ROL PROG R AM (PCP).......... ..................... ................ 6 25.
6.15 OFFSITE DOSE CALCULATlON MANUAL (ODCM)................................. 6-26 l l
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1.0 DEFINITIONS (Continued)-
OFFSITE DOSE CALCULATION MANUAL l 1.16 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and -
parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also i contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring :
Programs required by Section 6.8.4 and (2) descriptions of the information that should be l included in the Annual Radiological Environmental Operating and Semi annual Radioactive l Effluent Release Reports required by Specifications 6.9.1.8 and 6.9.1.9. l l
OPERABLE - OPERABILITY l
1.17 A system, subsystem, train, component.or device shall be OPERABLE or have .
OPERABILITY when it is capable of performing its specified function (s), and when all necessary .
attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other- auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable- of performing their related support function (s).
OPERATIONAL MODE - MODE 1.18 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination l of core reactivity condition, power level, and average' reactor coolant temperature specified in ;
Table 1.1.
PHYSICS TESTS 1.19 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and 1) described in Chapter 14.0 of the FSAR; 2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commission.
PRESSURE BOUNDARY LEAKAGE 1.20 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a non isolable fault in a Reactor Coolant System component body, pipe wall or vessel wall.
PROCESSCONTROLPROGRAM 1.21 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, tests and determinations to be made to ensure that the processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20,61, and 71, State regulations, burial ground requirements, and other requirements governing the-disposal of the radioactive waste. l l
PURGE - PURGING l l
1.22 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
1 NORTH ANNA - UNIT 1 1-4 Amendment No. ,
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1.0 DEFINITIONS (Continued)
OUADRANT POWER TILT RATIO 1.23 OUADRANT POWER TILT RATIO shall be the ratio of the maximum uppor excore detector '
calibrated output to'the average of the upper excore detector calibrated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater. With one excore detector inoperable, the remaining three detectors shall be used for computing the average. .i RATED THERMAL POWER 1.24 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor i coolant of 2893 MWt.
REACTOR TRIP SYSTEM RESPONSE TIME 1
1.25 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until loss of stationary gripper coil voltage.
REPORTABLE EVENT 1.26 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.
SHUTDOWN MARGIN 1.27' SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all- full length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn.
SITE BOUNDARY 1.28 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased or otherwise controlled by the licensee.
SLAVE RELAYTEST 1.29 A SLAVE RELAY TEST shall be the energization of each slave relay and verification of OPERABILITY of each relay. The SLAVE RELAY TEST shall include a continuity check, as a -
minimum, of associated testable actuailon devices.
SOURCECHECK 1.30 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to radiation. This applies to installed radiation monitoring systems.
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9 INSTRUMENTATION EXPLOSIVE GAS MONITORING INSTRUMENTATION ,
UMiTING CONDITIONS FOR OPERATION
. 3.3.3.11 The explosive gas monitoring instrumentation channels shown in Table 3.3-14 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.5 are not exceeded. ;
APPLICABILITY: As shown in Table 3.314.
ACTION.
- a. With an' explosive gas monitoring instrumentation channel alarm / trip setpo!nt less conservative than required by the above Specification, declare the channelinoperable, and take the ACTION shown in Table 3.3-14.
- b. With less than the minimum number of explosive gas monitoring instrumentation channels OPERABLE, for reasons other than a above, take the ACTION shown in Table 3.3-14. Exert best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 to explain why the inoperability was not corrected in a timely manner,
- c. The provisions of Specifications 3.0.3 and 3.0,4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.11 Each explosive gas monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CAllBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.314.
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-TABLE 3.314 EXPLOSIVE GAS MONITORING INSTRUMENTATION ;
MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION
- 1. DELETED
- 2. WASTE GAS HOLDUP SYSTEM EXPLOSIVEGAS MONITORING SYSTEM (Shared with Unit 2)
-l a.- Hydrogon Monitor '1- **
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- b. Oxygen Monitor 1 32 l-j During process vont system operation (treatment for primary system offgases).
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ACTION 32 - With the number of channels OPERABLE .less than required by the minimum -
channels OPERABLE requirement, operation of this' system may continue for up -
L to 14 days provided grab samples are taken and analyzed daily. With this channel inoperable, operation may continue provided grab samples are taken :
and analyzed: (1) every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during dogassing operations and-(2) daily- !
during other operations. i j
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NORTH ANNA - UNIT 1 3/4 3+60 Amendment No.
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l TABLE 4.3-14 ~
EXPLOSlVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODESIN WHICH t CHANNEL SOLBCE CHANNEL FUNCTIONAL SURVEILLANCE ;
INSTRUMENT CHECK CHECK CAllBRATION TEST REQUIRED !
- 1. DELETED 2, WASTEGASHOLDUP l SYSTEM EXPLOSIVE 1 GASMCNITORING i SYSTEM !
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- a. Hydrogen Monitor D N.A. O(3)- M "
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- b. Oxygen Monitor D N.A. .O(4) M During process vent system operation (treatment for primary system oligases) !
i (3 ) The CHANNEL CAllBRATION shall include the use of standard gas samples containing a !
nominal: ;
i 1 One volume percent hydrogen, balance nitrogen, and ;
( 4 ) The CHANNEL CAllBRATION shallinclude the use of standard gas samples containing a nominal: '
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NORTH ANNA - UNIT 1 3/4 11-1 Amendment No.
RADIQACTIVESTORAGE UQUID HOLDUP TANKS UMITING CONDITIONS FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each _of the following unprotected outdoor tanks shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.
- a. Refueling Water Storage Tank
- b. Casing Cooling Storage Tank
- c. PG Water Storage Tank *
- d. Boron Recovery. Test Tank' i
- e. Any Outside Temporary Tank" APPLICABILITY: At all times.
ACTION:
- a. With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable, SURVEILLANCE REOUIREMENTS _. _ , . . _
4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of-the tank's contents at least once per week when radioactive materials are being added to the tank.
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'ThisIs~a shared system with Unit 2.
" Tanks included in this Specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste ion exchanger system.
NORTH ANNA - UNIT 1 3/4 11-2 Amendment No.
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RADIOACTIVE STORAGE 3/4.11.2 GAS STORAGE EXPLOSIVE GAS MIXTURE LIMITING CONDITIONS FOR OPERATION 3.11.2.5 The concentration of oxygen in the waste gas decay tanks shall be limited to le3s than or equal to 2% by volume whenever the hydrogen concentration exceeds 4% by volume and is less than 96% by volume, APPLICABILITY: At all times.
ACTION:
- a. With the concentration of oxygen in the waste gas decay tanks greater than 2% by volume but less than or equal to 4% by volume, reduce the oxygen concentration to the above limits within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />,
- b. With the concentration of oxygen in the waste gas decay tanks greater than 4% volume and the hyorogen concentration greater than 2% by volume,' immediately suspend all-additions of waste gases to the system and reduce the concentration of oxygen to less -l than or equal to 2% by volume without delay,
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUlREMENTS 4.11.2.5 The concentrations of hydrogen and oxygen in the waste gas decay tanks shall be determined to be within the above limits by' continuously monitoring the waste gases in the waste gas decay tanks with the hydrogen and oxygen monitors required OPERABLE by Table 3.3-14 of Specification 3.3.3.11.
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l RADIOACTIVE STORAGE GASSTORAGETAtKS UMITING CONDITIONS FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to s 25,000 curies noble gases (considered as Xe-133).
- APPLICABILITY: At all times.
l ACTION:
- a. With the quantity of radioactive materialin any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit,
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVElLLANCE REOUIREMENTS 4.11.2.6 The quantity of radioactive material contained _in each gas storage tank shall be ,
determined to be within _the above limit at-least once per month when the specific activity of the . ;
primary reactor coolant is s 1.0 pCl/gm DOSE EQUIVALENT l 131. Under conditions which- i result in a specific activity > 1.0 Cl/gm DOSE EQUIVALENT l 131, the Gas Storage Tank (s) .{
shall be sampled once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, when radioactive materials are being added to the tank. 3 q
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3/4- 11-6
, LNORTH ANNA. UNIT 1 ' AmendmeritNo.
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1 Specifications 3/4,12.1 through 3/4,12.3 have-been deleted !
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h NORTH ANNA- UNIT 1 3/4 12 1 Amendment No.
._ = _ _ _ _ _ _ _ _ - _ - _ - _ _ _ - - . _ _ .
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I This Page Intentionally Left Blank ,
P NORTH ANNA UNIT 1 B 3/4 3 4 Amendment No.
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5
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r Specifications 3/4.11.1.1 through 3/4.11,1.3' have' been deleted
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l NORTH ANNA UNIT 1 B 3/4 11-1 Amendment No. l l
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RADIOACTIVESTORAGE <
'3/4.11.1 LIQUID STORAGE 1 l
BASES ~
l 3/4.11.1.4 LIQUID HOLDUP TANKS- J The tanks listed in this Specifica;lon iriclude all those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank centents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.
Restricting the quantity of radioactive material contained in the specified tanks provides
~
assurance that In the event of an uncontrolled release'of the tanks' contents, the resulting -
concentrations would be less than the limits of.10 CFR Part 20, Appendix B,' Table 11, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.
Specifications 3/4.11.2.i through 3/4.11.2.4 have been deleted.
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l NORTH ANNA - UNIT 1 B 3/4 11-2 Amendment No.
RADIOACTNESTORAGE l I
3/4.11:2 GAS STORAGE j i
j 3/4.11.2.5 EXPLOSlVE GAS MIXTURE j This Specification is provided to ensure that the concentration of potentially explosive- !
gas mixtures contained in the waste gas holdup system is maintained below the flammability limits of hydrogen and oxygen. Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be !
controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.
3/4.11.2.6 GAS STORAGE TANKS i
The tanks included in this Specification are those tanks for which the quantity of l radioactivity contained is not limited directly or indirectly by another Technical Specification i to a quantity that is less than the quantity which provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting total body exposure to an individual at i the nearest exclusion area boundary will not exceed 0.5 rem in an event of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.'
Restricting the quantity of radioactivity contained in each gas storage tank provides j assurance that in the event of an' uncontrolled release of the tank's contents, the resulting total ;
body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 rem. ;
This is consistent with Branch Technical Position ETSB 11-5 in NUREG-0800, July 1981.
Specifications 3/4.11.3 and 3/4.11.4 have been deleted.
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NORTH ANNA - UNIT 1 B 3/4 11-3 Amendment No.
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F Specifications 3/4.12.1 through 3/4.12.3 have been deleted .
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NORTH ANNA - UNIT 1 8 3/4 12-1 Amendment No.
I a
ADMINISTRATIVE CONTROLS ;
- e. - Radioactive Effluent Controls Proaram i
A program shall be provided conforming with 10 CFR 50.36a for the control of L radioactive effluents and for malntaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3)-
shall include remedial actions to be taken whenever the program limits are exceeded.
The program shall include the following elements: ,
e 1 ) Limitations on' the operability of radioactive liquid -and gaseous monitoring l instrumentation including surveillance tests' and setpoint determination in 2
accordance with the methodology in the ODCM, ,
2 ) Limitations- on the concentrations of' radioactive material released in. liquid elfluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table ll, Column 2, 3 t
3 ) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in t accordance with.10 CFR 20,106 and with the methodology and parameters in the-ODCM, 4 ) Limitations on the annual and quarterly doses'or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid' effluents released from each-unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50, _ l 5 ) Determination of cumulative and projected dose contributions from radioactive-effluents .for the current calendar quarter and current calendar yearlin i l
accordance with the methodology and parameters in the ODCM at least every 31 '
days, t
6 ) Limitations on the operability and use of the liquid and ' gaseous effluent treatment l.
systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31 day _ period .
L would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix 1 to 10 CFR Part 50, f
7 ) Limitations on the doso rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix B, Table 11, Column 1,-
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l NORTH ANNA - UNIT 1 6-13b Amendment No. )
1 2 .
ADMINISTRATIVE CONTROLS ,
- 8) Umitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNARY conforming to Appendix i to 10 CFR Part 50,
- 9) Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from lodine 131, lodine 133, tritium, and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR 50,
- 10) Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.
- f. Radiolooleni Environmental Monitorina Proaram A program shall be provided to monitor the radiation and radionuclides in the !
onvirons of the plant. The program shall provide (1) representative measurements i of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:
- 1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM, 2 ) A Land Uso Census to ensure that changos in the use of areas at and beyond tho l SITE BOUNDARY are id'ntified and that modifications to the monitoring program ,
are made if required by the results of this census, and '
l 3) Participation in a Interlaboratory Comparison Program to ensure that Independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part ;
of the quality assurance program for environmental monitoring. i j .
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NORTH ANNA UNIT 1 6 13 c Amendment No.
1 1
ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORI*
6.9.1.8 The Anneal Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3,and IV.C of Appendix I to 10 CFR Part 50.
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~~A~ single submittal r5y~E>o made for a multiple unit station.
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( NORTH ANNA UNIT 1 6 19 Amendment No. l
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ADMINISTRATIVE CONTROLS SEMIANNUAL RADIOLOGICAL EFFLUENT RELEASE REPORT
- 6.9.1.19 The Semlannual Radioactive Effluenf Release Report covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. The report shallinclude a summary of the quantitles of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outilhed in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.
L
- A single submittal may be made for a multi unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate ;
radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
NORTH ANNA UNIT 1 6 20 Amendment No.
_____-___--__----j
ADMINISTRATIVE CONTROLS (Continued) ,
SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator, Region 11, within the time period specified for each report. These reports shall be submitted pursuant to the .
requirement of the applicab!e specification:
- a. Inservice inspection Reviews, Specification 4.0.5, shall be reported within 90 days of completion.
- b. MODERATOR TEMPERATURE COEFFICIENT. Specification 3.1.1.4.
- c. RADIATION MONITORING INSTRUMENTATION. Specification 3.3.3.1, Table 3.3-6, Action 35.
- d. SEASMIC INSTRUMENTATION. Specifications 3.3.3.3 and 4.3.3.3.2.
- e. METEOROLOGICAL INSTRUMENTATION. Specification 3.3.3.4. ,
- f. FIRE DETECTION INSTRUMENTATION. Specification 3.3.3.7.
- g. LOOSE PARTS MONITORING SYSTEMS. Specification 3.3.3.9.
- h. REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY. Specification 3.4.8.
- l. OVERPRESSURE PROTECTION SYSTEMS. Specification 3.4.9.3.
- j. EMERGENCY CORE COOLING SYSTEMS. Specification 3.5.2 and 3.5.3.
- k. SETTLEMENT OF CLASS 1 STRUCTURES. Specification 3.7.12.
- l. GROUND WATER LEVEL SERVICE WATER RESERVOIR. Specification 3.7.13. '
- m. FIRE SUPPRESSION SYSTEMS. Specification 3.7.14.1, 3.7.14.2, 3.7.14.3, 3.7.14.4, and 3.7.14.6.
- n. RADIOACTIVE EFFLUENTS. As required by the ODCM.
- o. RADIOLOGICAL ENVIRONMENTAL MONITORING. As required by the ODCM. l I
I
- p. SEALED SOURCE CONTAMINATION. Specification 4.7.11.1.3.
- q. REACTOR COOLANT SYSTEM STRUCTURAL INTEGRITY. Specification 4.4.10. For any abnormal degradation of the structural integrity of the reactor vessel or the Reactor Coolant System pressure boundary detected during the performance of Specification 4.4.10, an initial report shall be submitted within 10 days after detection and a detailed report submitted within 90 days after the completion of Specification 4.4.10.
NORTH ANNA UNIT 1 6 21 Amendment No.
ADMINISTRATIVE CONTROUS r,_ Records of rev4ws performed for chan0es made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.
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i NORTH ANNA UNIT 1 6 23a Amendment No. ;
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1
ADMINISTRATIVE CONTROLS 6.13 DELETED 6.14 PROCESS CONTROL PROGRAM (PCP) 6.14.1 Changes to the PCP: 7
- 1. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2 r. This documentation shall contain:
a) Sufficient information to support the change together with the appropriate =
analyses or evaluations justifying the change (s) and b) A determination that the cl.;r.g; wltl .~ua;niain iiie overall conformance of the sohdified waste product to existing requirements of Federal, State, or -
other applicable regulations.
- 2. Shall become effective after revlow and acceptance by the SNSOC and the approval of the Plant Manager.
NORTH ANNA - UNIT 1 6 25 Amendment No.
ADMINISTRATIVE CONTROLS 8.15 OFFSITE DOSE CALCULATION MANUAL (ODCM)
Changes to the ODCM:
- a. Shall be documented and records of reviews performed shall be retained as required '
by Specification 6.10.2.r. This documentation shall contain: l 1 )- Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and _ 1
- 2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106,40 CFR Part 190,10 CFR 50.36a, and ;
Appendix ~ l to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
- b. Shall become effective after review and acceptance by the SNSOC and the approval of the Plant Manager.
- c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Semlannual Radioactive Effluent :
Release Report for the period of the report in' which any change to the ODCM was ,
made. Each change shall be identified by markings in the margin of the affected ,
pages, clearly indicating the area of the page that was changed, and shallindicate the 'I date (e.g., month / year) the change was implemented.
6.16 DELETED l 3
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I NORTH ANNA UNIT 1 6 26 Amendment No.
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Attachment 2 l
e Proposed Technical Specification Change .
, North Anna Unit 2 l-l i l
i Virginia Electric and Power Company i
JblDEX ;
SECTON Be2
.6 .
1.0 DEFINITIONS (continued) i R at ed T h erm al Powe r.. .. .... . .. .. . ... .. .. ..... . . .. .. . . . . .. .. . .. .. .. .... ... .. .. . .. . . .. .. ... . . . . .. .. ... ... . . . . . .. . 1 5 >
R eactor Trip System Re sponse Time............................................. . ........................ 1 5
- R e po rt able E v e n t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 ~ 5 i i
S h u id o w n M a r g i n . .. .. . . . . . . . . .. . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . .. . . .. . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 1 5 S i t e Bo u n da ry. . . .. .. . . . . . . .. . . . . . . . . . . . . .. . . . . . . . . . .. . . . . . . . . . . . . . . .. . . . .. . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . : 1. 5 1
Gl a v e R e l a y Te s t. . . . . . . . . . . . . . . . .. . . . . . . .. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1, 5 . !
[
So u r c e C h e ck. . . . . . . . . . . .. . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
S t ag g e red Te st B a sis . . . .... . . ... . . . .. . . .. . . . . . . . .. . . . ... . .. ... . . . ... . .. ... ... .. . .. . . .. .. . ..... . . .. ... .. . . . . ... .. . . . . 1 6 ' !
t i
T h e r m al P ow e r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . .. . .. . . . . . . . . . i
'1 U nid e n tifind Le ak ag e . . .. . . . . . .. .. .. . . ... .. .. .. . . . . . .. .. ... . . .. .. .. . .. .. .. ... .. . . .. ... . . . ... . .. . . . . .. . .. .. . . .. ... . . .. - 1 6 U n re st rict ed Are a. . . . . .. .. . . . . . . . . .. . .. . . . .. . .. . . . . . . .. . . . . . . . . .. .. . .. . .. . . . .. . . . .. . . . .. . .. .. . .. . .. .. . . . .. . .. . . . . .,. .. 1 - 6 !
Ventilation E xhaust Treatment Syste m.................................................................... 1 6 Veniing.....................................................................................................................J1.6 '
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,, NORTH ANNA UNIT 2 la . Amendment No.
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INDEX UMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REOUIREMENTS SECTION fBai :
3/4.2 POWER DISTRIBUTION UMITS 3/4.2.1 A xia l Flu x D itf e r e n ee . .. . .. ... . . . . . . .. . . . . . . . .. . .. . . . . . . . .. . .. . .. . .. . . . . .. . . . . . . . .. . .. . . . . . . . 3/4 21 3 / 4 . 2 . 2 H eat Flu x Hot C h a nnel Factor............................................................ 3/4 25 r
3 /4. 2.3 Nucleat Enthalpy Hot Channel Factor................................................ 3/4 29 -
3/4.2.4 Ou ad rant Power Tilt R a tio.... ..... ...... ...... .. .. .. .... ... .... .. ...... .... ..... .. .. .. .. .. 3/4- 2 12 3 / 4 . 2 . 5 D N B Pa r am e t e rs . . . . . . . . . . . . .. .. .. .. .. . . . . . . .. . . .. .. . . . . . . . . . . .. . . . . .. . . .. . . .. . . .. . . . . .. . . . . .. . . 3/4- 2 14 :
4 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION..... ............................... 3/4 31 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM I N ST R U M E N TAT I O N . . . .. . . . . .... . .. . .. . ... . . . . . . . .. . . . . . . . .. . . . . . . . .. ... . .. . . .. . . . . . . . . . . . . . . . 3/4 3 15 l 3/4.3.3 MONITORINGINSTRUMENTATION o
R a diat io n M o ni to rin g .. . . . .. . . . . . . . .. . . . . . . . . . .. . . . . . . . . . . . . . . . .. . . . . .. . .. . . . . . . .. . . . . . . . . . . . . . 3/4 3 38 M ovable I neo r e D e teeto rs.. .... . ....... .. .. .. .. .. .. .. .. .. .. .. .. .. .... .. . ... .... .. .. .... .. ... 3/4 3 42 Auxiliary Shutdown Panel Monitoring instrumentatlon.................... 3/4 3 43 Accident Monitoring Instrumentallon................................................. 3/4 346-Fire Detectio n In strumentatio n.......................................................... 3/4 3 49 Explosive Gas Monitoring Instrumentation........................................ 3/4 3 52 f
9 3/4 4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION S t a rt up and Power Ope ration............... ........................................ ...... 3/4 41 HotStandby............................................................................ 3/4 4-2 Shutdown......................................................................................... 3/4 43 I s ol a t e d Lo o p . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4
. . . . . . . . 44 I sola t e d Lo o p S t a rt u p. .. . . . . . . . . . . . . .. . . . . . . . . . . . . . . .. . . . . . . . . . . . .. . . . . . . . . . . . . . .. . . .. . . . . . . . . 3/4 45 NORTH ANNA- UNIT 2 IV Amendment No.
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l INDEX UMITING CONDITIONS FOR OPERATION AND SURVEILLANCE PEQUIREMENTS SECTK)N P82 3/4.11 RADIOACTIVE STORAGE 3/4.11.1 UQUID STORAGE Liq uid H old up T an ks .. ... . . . . .. . .. . . . .. . . .. .... .. . ... . . . . ... . . . . .. .. . . . . . .. . . . .. ... ... . . . . 3/4 11 2 3/4.11.2 (MSSIORAGE <
t E x plo sive G a s M i x t u r e . . . . .. . . . . .. . . . .. . . . . .. . .. .. .. . .. . . . . . . .. . .. .. .. .. . . . . . . . . . . .. .. . . . . 3/4 11 4 G a s Sto r ao e Ta nks .... .. . . . .. . . . .. .. .. . . . . .. .. . .. . . .. . .. . . . . . . . . . .. .. .. . . . . . . ... 3/4- .... .. . .11
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NORTH ANNA UNIT 2 X Amendment No.
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SECTION E82 3/4.11 RADIOACTIVE STORAGE 3/4.11.1 LIO U l D STO R AG E...... ... .... ... . . .. .... .... ... . . ...... ... ........ . .. .. .. ... . . . . . . . ... . .. B 3/4 11 2 3/4.11.2 G A S S TO R AG E . . . .. . . . . . . . . . . .. . . . . . . . . . .. . . . . .. . . . . . .. .. . . .. . . . . . . .. . . . . . . . . . . . .. . . . . . . . . . . .. . B 3/4 11-3 i
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l NORTH ANNA UNIT 2 XIVa Amendment No. I I
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i INDEX l ADMINISTRATIVE CONTROLS i
i SECTDON E6E i 69 C o n s u l t a n ts . . . . . . . . . . . .. . . . . . . . . . . . .. . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . i
' M e etIn g F requ e n cy.. .. .. . . . . . . .. .. .. . .. .. .. .. .. .. . . .. . . . .. .. .. .. .. . . . .. .. . .. . . . .. .. .... .. . .. .. . . .. 69 Review................................................................................................... 69 1 Authority............................................................................................... 6 10 j Records.................................................................................................. 6'10 i 6.5.3 OUALITY ASSURANCE DEPARTMENT I Function................................................................................................. 6 11 .
Authority............................................................................................... 6-12 Records................................................................................................. 6 12 6.6 R E PO RTAB LE E V E NT ACT IO N .. . .. . ... .... . ... . . ......... .. .... . .. .. . . ... .. ..... .... . ... . ..... 6 13 6.7 S AF ETY Li M IT VIO LATI O N . . . . . . . . .. . ... .. ... . . . . . . .. .. . . ..... . .... ... .... ... . .. . . . ... . . .. . .. ... 6 13 6.8 P ROC E D U R E S AN D P R OG R AM S .... ... . .. . .. . .. ........ ... ......... . . . . ... .. ... .. ... ... ... .. . 6 13-6.9 REPORTING REQUIREMENTS ,
6.9.1 R O UTI N E R E P O RTS . . .. .. .. . . . .. ... . .. . . . . . . . . .. . .. . . . . . . . ... . . . .... ... . .. . .. . .. . . . .. . .. . . .. . . .6 . 14' 6 . 9 . 2 S P EC I A L R E P O R T S . .. .. . . . .. .. . . . .. . . . . . .... .. . . .. . . . . ... .. . . .. .. . . . . .. . .. . .. . ... . .. . ... . ... .. . . 6-21 6.10 R E C O R D R E T E NT 10 N ... ... .. . . . . . .. . . . .. .... ... . . . . . . . . . . . . . .. . . . . . . . .. . . . . . . . .. .... ... . 6 . . ..22 6.11 RADI ATION P ROTECTION P ROG R AM........................................ ........... 6 24 6.12 H I G H R A DI AT I ON A R E A . . .. . . . . . . .. . . .... .. . . .... . .. . . . . .. . .......... . . .... ... ...... ... . . .6. .. 24 ..
6.13 PROC ESS CONT ROL PROG R AM (PCP)................................................. 6-25 6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM)................................. 6 25 I
NORTH ANNA UNIT 2 XVil Amendment No.
1.0 DEFINITIONS (Continued)
OFFSITE DOSE CALCULATION MANUAL 1.16 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid i effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and ;
in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Semi annual Radioactive Effluent Release Reports required by Specifications 6.9.1.8 and 6.9.1.9.
OPERABLE OPERABILITY 1.17 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or ;
seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of ,
performing their related support function (s).
OPERATIONAL MODE - MODE 1.18 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.1.
PHYSICS TESTS 1.19 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and 1) described in Chapter 14.0 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise ,
approved by the Commission.
PRESSURE BOUNDARY LEAKAGE 1.20 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a non isolable fault in a Reactor Coolant System component body, pipe wall or vessel wall.
PROCESS CCNTROL PFF3 GRAM 1.21 The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, tests and determinations to be made to ensure that the processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes wlil be accomplished in such a way as to assure compliance with 10 CFR Parts 20,61, l and 71, State regulations, burial ground requirements, and other requirements governing the disposal of the radioactive waste.
PURGE - PURGING 1.22 PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
NORTH ANNA UNIT 2 14 Amendment No.
l
i 1.0 DEFINITIONS (Continued) ,
OUADRANT POWER TILT RATIO 1.23 OUADRANT POWER TILT RATIO shall be the ratio of the maximum upper excore detector j calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of !
the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater. With one excore detector inoperable, the remaining three detectors shall be used for computing the average.
RATED THERMAL POWER 1.24 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2893 MWt.
REACTOR Trio SYSTEM RESPONSE TIME 1.25 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until loss of stationary gripper coil voltage.
REPORTABLEEVENT 1.26 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.
SHUTDOWN MARGIN 1.27 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be suberitical from its present condition assuming all full length rod cluster assemblies (shutdown ord control) are fully inseited except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn.
SITE BOUNDARY ,
1.28 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased or otherwise controlled by the licensee.
SLAVE RELAY TEST 1.29 A SLAVE RELAY TEST shall be the energization of each slave relay and verification of OPERABILITY of each relay. The SLAVE RELAY TEST shall include a continuity check, as a minimum, of associated testable actuation devices.
SOURCECHECK 1.30 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to radiation. This applies to installed radiation monitoring systems.
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NORTH ANNA UNIT 2 1-5 Amendment No.
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INSTRUMENTATION f)(PLOStVE GAS MONITORING INSTRUMENTATION l
LIMITING CONDITIONS FOR OPERATION 3.3.3.11 The explosive gas monitoring instrumentation channels shown in Table 3.313 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.5 are not exceeded.
APPLICABILITY: As shown in Table 3.3-13 ACTION.
I a. With an explosive gas monitoring instrurnentation channel alarm / trip sotpoint loss conservativo than required by tho above Specification, doctaro the channel inoperablo, 4 and take the ACTION shown in Table 3.313.
- b. With less than the minimum number of explosivo gas monitoring instrumentation channels OPERABLE, for reasons other than a above, take the ACTION shown in Table 3.3 13. Exort best efforts to return the instruments to OPERABLE status within 30 days and, if unsuccessful, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 to explain why the inoperability was not corrected in a timely manner.
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
( SURVEILLANCE REOUIREMENTS 4.3.3.11 Each explosive gas monitoring instrumentation channel shall bo demonstrated l OPERABLE by performance of the CHANNEL CHECK, CHANNEL CAllBRATION and CHANNEL '
FUNCTIONAL TEST operations at the frequencies shown in Tablo 4.3-13.
l NORTH ANNA UNIT 2 3/4 3 52 Amendment No.
TABLE 3.313 f 1
EXPLOSIVE GAS MONITORING INSTRLMENTATION {
MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION !
- 1. DELETED
- 2. WASTEGASHOLDUPSYSTEM EXPLOSIVEGAS MONITORING SYSTEM (Shared with Unit 2)
- a. Hydrogen Monitor 1 .32
- b. Oxygen Monitor 1 32 During process vent system operation (treatment for primary system offgases)..
ACTION 32 - With the number of channels OPERABLE less than required by the minirnum channels OPERABLE requirement, operation of this system may continue for up to 14 days provided grab samples are taken and analyzed daily. With this channel inoperable, operation may continue provided grab samples are taken and analyzed: (1) every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during degassing operations and (2) daily during other operations.
NORTH ANNA - UNIT 2 3/4 3 53 Amendment No..
- . -i
i TABLE 4.313 - ,
EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILt.ANCE REQUIREMENTS CHANNEL MODES IN WHICH .
CHANNEL 93URT CHANNEL FUNCTIONAL SURVEILLANCE ,
INSTRUMENT CHECK CHECK CAUBRATION TEST REQUIRED i
- 1. DELETED
- 2. WASTEGASHOLDUP SYSTEM EXPLOSIVE GASMONITORING SYSTEM ,
N.A; "
- a. Hydrogen Mon % D O(3) M
- b. Oxygen M- w D N.A. O(4) M "
During process vent system operation (treatment for primary system offgases)
( 3) The CHANNEL CAllBRATION shallinclude the use of standard gas samples containing a i nominal:
(4 ) The CHANNEL CALIBRATION shallinclude the use of standard gas samples containing a nominal:
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NORTH ANNA UNIT 2 3/4 3 54 Amendment No.
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Specifications 3/4.11,1,1 through 3/4.11,1,3 have been deleted NORTH ANNA UNIT 2 3/4 11 1 Amendment No.
RADIQACTIVE STORAGE j LIQUID HOLDUP TANKS UMITING CONDITIONS FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each of the following unprotected outdoor tanks shall be limited to less than or equal to 10 curies, excluding tritium and dissolved ,
or entrained noble gases. -
- a. Refueling Water Storage Tank
- b. Casing Cooling Storage Tank '
- c. PG Water Storage Tank'
- d. Boron Recovery Test Tank * '
- e. Any Outside Temporary Tank" APPLICABILITY: At all times.
ACTION:
- a. With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit,
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable, q
' SURVElLLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per week when radioactive materials are being added to the tank.
'This is Ishared system with IJnit 2.
" Tanks included in this Specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste ion exchanger system.
1 NORTH ANNA- UNIT 2 3/4 11-2 Amendment No.
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I RADIOACTIVE STORAGE )
l 3/4.11.2 GAS STORAGE t
l EXPLOSIVE GAS MIXTURE i
UMITING CONDITIONS FOR OPERATION _
3.11.2.5 The concentration of oxygen in the waste gas decay tanks shall be limited to less than ,
or equal to 2% by volume whenever the hydrogen concentration exceeds 4% by volume and is less than 96% by volume.
APPLICABILITY: At all times.
ACTION:
- a. With the concentration of oxygen in the waste gas decay tanks greater than 2% by volume but less than or equal to 4% by volume, reduce the oxygen concentration to the above limits within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />,
- b. With the concentration of oxygen in the waste gas decay tanks greater than 4% volume and the hydrogen concentration' greater than 2% by volume, immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than or equal to 2% by volume without delay.
- c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REOUIREMENTS 4.11.2.5 The concentrations of hydrogen and oxygen in the waste gas decay tanks shall be determined to be within the above limits by continuously monitoring the waste gases in the waste gas decay tanks with the hydrogen and oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.11.
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l NORTH ANNA UNIT 2 3/4 11 4 Amendment No.
RADIOACTIVE STORAGE GASSTORAGETAtKS LIMITING CONDITIONS FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to s 25,000 curies noble gases (considered as Xe-133).
APPlICABillTY: At all times.
ACTION:
- a. With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit,
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. l
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SURVEILLANCE REQUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per month when the specific activity of the primary reactor coolant is s 1.0 pCl/gm DOSE EQUIVALENT l 131. Under conditions which ;
result in a specific act;vity > 1.0 pCl/gm DOSE EQUIVALENT l-131, the Gas Storage Tank (s) l shall be sampled once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, when radioactive materials are being added to the tank. '
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4 Specifications 3/4,11.1.1 through 3/4.11,1.3 have been deleted E
Amendment No. .l B 3/4 11 1 !
NORTH ANNA UNIT 2 ,
Specifications 3/4,11.1.1 through 3/4.11.1.3 have been deleted
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NORTH ANNA- UNIT 2 B 3/4 11 1 Amendment No, t
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RADOACTIVE STORAGE 3/4.11.1 LIQUID STORAGE i
BASF3 3/4.11.1.4 LIQUID HOLDUP TANKS The tanks listed in this Specification include all those outdoor tanks that are-not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.
Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table li, Column 2, '
at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.
.i Specifications 3/4.11.2.1 through 3/4.11.2.4 have been deleted.
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1 NORTH ANNA - UNIT 2 B 3/4 11 2 Amendment No.
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RADOACTIVE STORAGE 3!4.11.2 GAS STORAGE i
i praaace.y w~< '
3/4.11 QQEi,f$1VE GAS MIXTl'AE This Specification is provided to ensu!c inal the concentation of potentially explosive gas mixtures contained in the waste gas holdup system is maintained below the flammability limits of hydrogen and oxygen. Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the 7equirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.
3/4.11.2E GAS STORAGE TANKS The tanks included in this Specification are those tanks for which the quantity of l
radioactivity contained is not limited directly or indirectly by another Technical Specification to a quantity that is less than the quantity which provides assurance that in the event of an ,
i uncontrolled release of the tank's contents, the resulting total body exposure to an Individual at the nearest exclusion area boundary will not exceed 0.5 rem in an event of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
Restricting the quantity of radioactivity contained in each gas storage tank provides !
assurance that in the event of an uncontrolled release of the tank's contents, the resulting total <
body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 rem. t This is consistent with Branch Technical Position ETSB 115 in NUREG 0800, July 1981.
Specifications 3/4.11.3 and 3/4.11.4 have been deleted.
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a NORTH ANNA - UNIT 2 B 3/4 11-3 Amendment No.
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Specifications 3/4.12.1 through 3/4.12.3 have been deleted !
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1 NORTH ANNA - UNIT 2 B 3/4 12-1 Amendment No.
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ADMINISTRATIVE CONTROLS-
- e. Radioactive Effluent Controls Procram j
l A program shall be provided conforming with_10 CFR 50.36a for the control of-
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radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from j radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3)
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shall include remedial actions to be taken whenever the program limits are exceeded. j The program shall include the following elements' i l
l 1 ) Limitations on the operability of radioactive liquid and gaseous monitoring ;
instrumentation !ncluding surveillance tests and setpoint determination. in -
accordance with the methodology in the ODCM, '
=4 2 ) Limitations on the ^ concentrations of radioactivo material released in liquid j effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table ll, Column 2, 3 ) Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in-
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i accordance with 10 CFR 20.106 and with the methodology and parameters in the -
ODCM, .
l 4 ) Limitations'on the annual and quarterly doses or dose commitment to a MEMBER l OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix.l to 10 CFR Part 50, I
j 5 ) Determination of cumulative and projected done contributions from radioactive effluents for the current calendar quarter and current : calendar -year in 1 accordance with the methodology and parameters in the ODCM at least every 31 days,
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6 ) Limitations on the operability and use of the liquid and gaseous effluent treatment j systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the-projected doses in a 31 day period
.would exceed 2 percent of the guidelines for the annual dose or dose commitment 4
conforming to Appendix I to 10 CFR Part 50, 7 ) Limitations on the dose rate resulting from radioactive material released in i gaseous effluents to areas beyond the SITE BOUNDARY' conforming to the doses associated with 10 CFR Part 20, Appendix B, Table 11, Column 1,
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NORTH ANNA - UNIT 2 6-13b Amendment No.
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ADMINISTRATIVE CONTROLS (l
6.8.4 e. Radioactive- Effluent Controls Prooram'(Cont 3
- 8) Limitations on the annual and quarterly air ' doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNARY i conformhg to Appendix I to 10 CFR Part 50, !
- 9) Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from lodine 131 lodine 133, tritium,- and- all radionuclides in . particulate 1
form with half lives greater than 8 days in gaseous effluents released from j each unit to areas beyond the SITE BOUNDARY conforming to Appendix l to 10 CFR 50, i
- 10) Umitations on the annual dose or dose commitment to any MEMBER OF THE .
PUBLIC due to releases of radioactivity and to radiation from. uranium fuel !
cycle sources conforming to 40 CFR Part 190.
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f, Radioloaical Environmental Monitorina Procram A program shall be provided'to monitor the radiation and radionuclides in the environs of the plant. The program shall' provide (1). representative measurements ;
of radioactivity in the highest potential exposure pathways, and (2) verif.ication of -
the accuracy of the effluent monitoring program and modeling of environmental ~ '
exposure pathways. The program shall (1) be: contained in the ODCM,'(2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following: ;
- 1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in' the environment in accordance with the methodology and parameters in the i ODCM,
- 2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and
- 3) Participation in a .interlaboratory Comparison Program to ensure that independent checks on the precision and' accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.
NORTH ANNA - UNIT 2 6-13c Amendment No.
ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
- 6.9.1.8 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The ;
report shall include summaries, interpretations, and analysis of trends of the results of the l Radiological Environmental Monitoring Program for the reporting period. The material i provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections 1 IV.B.2, IV.B.3,and IV,C of Appendix I to 10 CFR Part 50.
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- A single submittal may be made for a multiple unit station.
NORTH ANNA-UNIT 2 6 19 Amendment No.
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ADMINISTRATIVE CONTROLS SEMIANNUAL RADIOLOGICAL EFFLUENT RFi FASE REPORT
- 6.9.1.19 The Semlannual Radioactive Effluent Release Report covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. The report shall include a summary of the quantitles of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance
- with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.~
A single submittal may be made for a multi unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
NORTH ANNA UNIT 2 6-20 Amendment No.
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- ADMINISTRATIVE CONTROLS (Continued)
SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator, Region 11, within the time period specified for each report. These reports shall be submitted pursuant to the requirement of the applicable specification:
- a. Inservice inspection Reviews, Specification 4.0.5, shall be reported within 90 days of completion,
- b. MODERATOR TEMPERATURE COEFFICIENT. Specification 3.1.1.4.
- c. FIRE DETECTION INSTRUMENTATION, Specification 3.3.3.7, .
- d. RADIATION MONITORING INSTRUMENTATION. Specif; cation 3.3.3.1, TABLE 3.3 6 Action 35,
- e. REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY, Specification 3.4.8.
- f. OVERPRESSURE PROTECTION SYSTEMS. Specification 3.4.9.3.
- g. EMERGENCY CORE COOLING SYSTEMS. Specification 3.5.2 and 3.5.3
- h. SETTLEMENT OF CLASS 1 STRUCTURES. Specification 3.7.12.
- i. GROUND WATER LEVEL SERVICE WATER RESERVOIR. Specification 3.7.13.
- j. FIRE SUPPRESSION SYSTEMS. Specification 3.7.14.1, 3.7.14.2, 3.7.14.3, 3.7.14.4, 3.7.14.5 and 3.7.14.6.
- k. PENETRATION FIRE BARRIERS. Specification 3.7.15.
- l. RADIOACTIVE EFFLUENTS. As required by the ODCM.
- m. RADIOLOGICAL ENVIRONMENTAL MONITORING. As required by the ODCM.
- n. SEALED SOURCE CONTAMINATION. Specification 4.7.11.1.3.
- o. REACTOR COOLANT SYSTEM STRUCTURAL INTEGRITY, Specification 4.4.10. For any abnormal degradation of the structural integrity of the reactor vessel or the Reactor i
Coolant System pressure boundary detected during the performance of Specification 4.4.10, an initial report shall be submitted within 10 days after detection and a 1 detailed report submitted within 90 days after the completion of Specification 4.4.10.
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- p. CONTAINMENT STRUCTURAL INTEGRITY. Specification 4.6.1.6. For any abnormal degradation of the containment structure detected during the performance of Specification 4.6.1.6, an initial report shall be submitted within 10 days after completion of Specification 4.6.1.6. A final report, which includes (1) a description of the condition of the liner plate and concrete, (2) inspection procedure, (3) the ,
tolerance on cracking, and (4) the corrective actions taken, shall be submitted within 90 days after the completion of Specification 4.6.1.6.
NORTH ANNA - UNIT 2 6-21 Amendment No.
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ADMINISTRATIVE CONTROLS
- g. Records of reactor tests and experiments.
- h. Records of training and qualification for current members of the plant staff.
- 1. Records of in service inspections performed pursuant to these Technical Specifications. -
J. Records of. Quality Assurance activities required by the OA Manual,
- k. Recoords of the service life of all hydraulic and mechanical snubbers required to be operable by Technical Specification 3.7.10 including the date at which the service life commences and associated installation and maintenance records;
- l. Records of review performed for changes made to procedures or equipment or !
reviews of tests and experiments pursuant to 10 CFR 50.59. '!
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- m. Records of meetings'of the SNSOC.
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- n. Records of meetings of the System Nuclear Safety and Operating Committee to j
-Issuance' of Amendment No.11. -
- o. Records of Secondary water sampling and water quality.
- p. Records for Environmental Qualification which are covered under the ' provisions ;
of Paragraph 2.C(4) (3) of License No. NPF-7. j
- q. Records of analyses required by the radiological environmental monitoring program !
that would permit evaluation of the accuracy of.the analysis at a later date. This !
would included procedures effective at specified times and QA records showing that these procedures were followed.
- r. Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM. ;
q 6.11 RADIATION PROTECTION PROGRAM i i
Procedures for personnel radiation protection shall be - prepared consistent with the k requirements of.10 CFR Part 20 and shall be approved, maintained and adhered to for all '
operations involving personnel radiation exposure.
6.12 HIGH RADIATION AREA 6,12.1 In lieu of the " control device" or " alarm signal" required by paragraph '20.2,03(c) (2) ,
of 10 CFR 20, each high radiation area in which-the intensity of raciation is greater than 100 l mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted a high radiation area and entrance i l
- NORTH ANNA - UNIT 2 6-23 Amendment No.
1 ADMIN!STRATIVE CONTROLS' 6.13 PROCESS CONTROL PROGRAM (PCP) j Changes to the PCP:
s a.
Shall be documented and records of reviews performed shall be retalried as required by Specification 6.10.2.r. This documentation shall contain.
- 1) Sufficient information' to support the change together with the appropriate analyses or evaluations justifying the change (s) and-2 )- A determination that the change will maintain the overall conformance oi the -
solidified waste product to existing requirements of Federal, State, or other.
applicable regulations.
- b. _ Shall become effective after review and acceptance by the SNSOC and the approval of-the Plant Manager, I L
.i 6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) I 2
Changes to the ODCM: l a.
Shall be documented and records of-reviews performed shall be retained as required- '
by Specification 6.10.2.r. This documentation shall contain:
- 1) .
Sulficient information to support. the change together with the- appropriate-. .i analyses or evaluations justifying the change (s) and
- 2) A determination that the change will maintain the level of radioactive effluent d control required by 10 CFR 20.106, 40 CFR Part 190,10 GFR 50.36a, and l
Appendix I to 10 CFR Part 50 and not adversely Impact'the accuracy or reliability of effluent, dose, or setpoint calculations. '
b.
Shall become effective after review and acceptance by the SNSOC and the approval of the Plant Manager.
- c. 1 Shall be submitted to the Commission in the form of a complete, legible copy of the i entire ODCM as a part of or concurrent with the Semlannual Radioactive Effluent l
Release Report for the period of th9 repert in which any change to the ODCM was made. x Each change shall be Dntified by markings in the margin of the affected - r pages, clearly indicating the area on the page that was changed, and shall Indicate the date (e.g., month / year) the change m's implemented.
b 6.15 DELETED I
i NORTH ANNA - UNIT 2 6-25 Amendment No.
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Attachment 3 e
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Discussion of Proposed Change .
North Anna, Units 1 and 2 :
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b Virginia Electric and Power Company I
o Discussion of Proposed Technical L
Specification- Change introduction j
. - I The proposed changes to the North Anna Units 1~ and 2 Technical Specifications relocates the Radiological Effluent Technical Specifications. These specifications-are .
being moved to the Offsite Dose Caculation Manual (ODCM) or the Process Control j Program (PCP). Technical Specifications relating to these documents are also being i amended due to their expanded role, i i
Background .l This proposed change is based on the NRC's Generic Letter 89-01 dated January 31, 1989. The letter stated that the NRC will approve .a Technical Specification amendment to delete the Radiological Effluent Technical Specifications if the '
i requirements are relocated to the ODCM or PCP. The letter was very specific about what changes are acceptable and warned that proposed amendments that deviate- '
from its guidance will require a longer, more detailed review. It stated that conforming
- amendment requests will be expeditiously reviewed. This proposed change follows the guidance in the letter. Some minor changes were needed due to differences i between North Anna and Standard Technical Specifications.
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- Descriotion of the Proposed ~ Change ,
- 1. The following items are deleted from the index:
Under section 1.0 " solidification" L Under section 3/4.3.3 " Radioactive Liquid Effluent Monitoring Instrumentation.
Under section 3/4.11.1:
" Concentration" ,
" Dose" l " Liquid Radwaste Treatment" Under section 3/4.11.2:
" Dose Rate"
" Dose - Noble Gases" ,
" Dose lodine - 131, Tritium, and Radionuclides in Particulate Form" '
" Gaseous Radwaste Treatment" Section 3/4.11.3 Section 3/4.11.4 Section 3/4.12 and all subsections Bases section 3/4.11.3 Bases section 3/4.11.4 i Bases section 3/4.12 and all subsections p Section 6.16 (6.15,for Unit 2)
- 2. In the index under section 3/4.3.3 " Radioactive Gaseous Effluent" is changed to l " Explosive Gas "
l L 3. In the index, the word " Effluents" in item 3/4.11, 3/4.11.1 and 3/4.11.2 is changed to " Storage" and " Gaseous" in item 3/4.11.2 is changed to " gas." The
! same changes are made to the bases index items.
- 4. Specification 1.16, the ODCM definition, is replaced with' item number 1.17 from Enclosure 3 of the Generic. Letter, except references to Specifications 6.9.1.3 and 6.9.1.4 are changed to 6.9.1.8 and 6.9.1.9. The revision reflects the expanded role of the ODCM.
- 5. Specification 1.21, the PCP definition, is replaced with item number 1.22 from Enclosure 3 of the Generic Letter. This adds references to 10CFR61 and burial ground requirements which were previously included in "other requirements." ;
- 6. Section 1.29 is deleted. The requirements are added to the PCP.
- 7. Sections 3.3.3.10 (3.3.3.9 for Unit 2) and 4.3.3.10 are deleted. The requirements are added to the ODCM.
- 8. Although not reflected in the title, Specifications 3.3.3.11 (3.3.3.10 for Unit 2) and 4.3.3.11 cover explosive gas storage in addition to radioactive gaseous effluents. The change deletes effluent monitoring requirements, which have been added to the ODCM, but retains the explosive monitoring requirements.
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1 8a. Unit 2 Specification 3.3.3.10 is renumbered 3.3.3.11 for consistency with its. ,
corresponding surveillance requirement and Unit 1.
8b. The phrase " radioactive gaseous effluent" in the title of Specification 3.3.3.11
l and Tables 3/4.314 (Unit 1) and 3/4.3-13 (Unit 2) and the first sentences of .
3.3.3.11,3.3.3.11a,3.3.3.11b and 4.3.3.11 is replaced with " explosive gas."
8c. The reference to Specification 3.11.2.1 in 3.3.3.11 is changed to 3.11.2.5.
8d. 'The last sentence of 3.3.11, before " Applicability" is deleted.
8e. "With a" in 3.3.3.11a is changed to "With an."
8f. The phrase "without delay suspend the release of radioactive gaseous effluents monitored by the affected channel or" in 3.3.3.11a is deleted.
8g, The phrase "or change the setpoint so it is acceptably conservative"in 3.3.3.11a is replaced with" and take the ACTION shown in Table 3.314." -
8h, The. phrase " explain in the next Semiannual. Radioactive Effluent' Release.
Report" in 3.3.3.11b is replaced with " prepare and submit a Special Report to
..the Commission pursuant to Specification 6.9.2 to explain."
- 81. The phrase " SOURCE CHECK"in 4.3.3.11 is deleted.
8J. Items 1,3 and 4 in Table 3.3.14 are deleted.
8k. In-Table 3.314 Table. Notation the phrase "* At'all times" and paragraphs for ACTION numbers 30,31,31 A,33 and 34 are deleted.
- 81. Items 1,3 and 4 in Table 4.3-14 are deleted.
8ml. Items *,1,2 and 5 in Table 4.3-14 Table Notation are deleted.
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- 9. The word " Effluents" in the titles of sections 3/4.11, 3/4.11.1 and 3/4.11.2 is changed to " Storage."
- 10. All subsections of 3/4.11.1 and 3/4.11.2 except_3/4 i).1.4 " Liquid Holdup
,. Tanks," 3/4.11.2.5 " Explosive Gas Mixture" and 3/4.112.6 " Gas Storage Tanks" I are deleted. l
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- 11. All of section 3/4.12 " Radiological Environmental Monitoring" is deleted.
, 12. The word " Effluents" in the titles of Bases sections 3/4.11,2/4.11.1 and 3/4.11.2 l Is changed to " Storage." '
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- 13. The Bases for sections 3/4.3.3.9, 3/4.3.3.10, 3/4.11.1.1, 3/4.11.1.2, 3/4.11.1.3, 3/4.11.2.1, 3/4.11.2.2, 3/4.11.2.3.. 3/4.11.2.4, 3/4.11.3, 3/4.11.4, 3/4.12.1, 3/4.12.2 and 3/4.12.3 are deleted,
- j. :14. A new Specification,6.8.4e " Radioactive Effluent Controls Program,"is added.
This is the same as the Specification 6.8.4g in Enclosure 3 of Generic Letter 89-01 except paragraph- 10, which is not applicable to PWRs, is omitted _and paragraph 11 is. renumbered:10. The new section contains: administrative.- .
controls removed from 3/4.11. j
- 15. A new Specification,6.8.4f " Radioactive Environmental Monitoring Program," is i added. This is the same as Specification 6.8.4h.in Enclosure 3.of the Generic 'l Letter. The new section contains administrative controls that were in 3/4.12. 1 i
- 16. Specification 6.9.'1.8 "Annuai Radiological Environmental Operati.ng Report" is !
replaced with the corresponding 6.9.1.3 from Enclosure 3 of the Generic Letter. !
- 17. Specification 6.9.1.9 " Semiannual Radioactive Effluent Release Report" is replaced with the corresponding 6.9.1.4 from Enclosure 3 of the Generic Letter.
The replacement Specifications 6.9.1.8 and 6.9.1.9 are more simple and general. The details have been relocated to the ODCM.
- 18. In' Unit 1 Specification 6.9.2.n and= Unit 2 Specification 6.9.2.1, the phrase !
" Specifications 3.11.1.2, 3.11.1.3, 3.11.2.2, 3.11.2.3, 3.11.2.4 and 3.11.4" is j changed to "as required by the ODCM." j 1
- 19. In Unit 1 Specification 6.9.2.0 and Unit 2 Specification 6.9.2.m,- the phrase !
" Specification 3.12.1.b" is replaced with "As required by the ODCM."
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L 20. Under 6.10.2, records to 'be retained for the duration of the license, a new section r is added: ;
- r. Records of reviews performed for changes made to the OF? SITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.
- 21. Section 6.14.1, which deals with PCP changes, is replaced with 6.13 from ';
Enclosure 3 of the Generic Letter, except that reference to 6.10.3o is changed to .
6.10.2r and "URG" is changed to "SNSOC." This removes the requirement that we send changes to the NRC and adds the requirement that they be approved by the Plant Manager.
- 22. Section 6.15 "Offsite Dose Calculation Manual (ODCM)" is replaced with the corresponding section 6.14.from Enclosure 3 of the Generic Letter except that reference to 6.10.30 is changed to 6.10.3r and."URG' is changed to "SNSOC."
This adds the requirement that the Plant Manager approve changes. Also instead of sending changes to the NRC, complete documents are submitted.
- 23. Section 6.16 " Major Changes to Radioactive Solid Waste Treatment Systems" and all subsections are deleted.
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Safety Analysis Although the proposed changes simplify the Technical Specifications, there is no '
reduction in requirements because of additions to the ODCM and PCP It therefore meets the requirements for a Technical Specification change. The following table- !
outlines the disposition of each requirement removed from the Technical Specifications.
Specification Addition. l 1,29 PCP 3/4.3.3.10 ODCM 6.2.2 TS 6.8.4.e.1 3/4.3.3.11 (except explosive gas) ODCM 6.3.2 i 1
TS 6.8.4.e.1 3/4.11.1.1 ODCM 6.2.1 TS 6.6.4.e.2 3 3/4.11.1.2 ODCM 6.2.3 i TS 6.8.4.e.4-5 3/4.11.1.3 ODCM 6.2.4 ;
TS 6.8.4.e.6 i 3/4.11.2.1 ODCM 6.3.1 l TS 6.8.4.e.3 TS 6.8.4.e 7 3/4.11.2.2 ODCM 6.3.3 4
- TS 6.8.4.e.5' ]
TS 6.8.4.e.8 !
3/4 11.2.3 ODCM 6.3.4 }
TS 6.8.4.e.5 .l TS 6.8.4.e.9 'l 3/4.11.2.4 ODCM 6.3.5 '
TS 6.8.4.e.6 i 3/4.11.3 PCP i 3/4.11.4 ODCM 6.4 TS 6.8.4.e.10 j 3/4.12.1 ODCM 6.5.1 TS 6.8.4.f.1 ,
3/4.12.2 ODCM 6.5.2 1 TS 6.8.4.f.2 3/4.12.3 ODCM 6.5.3 TS 6.8.4.f.3 6.9.1.8 ODCM 6.6.1 k 6.9.1.9 ODCM 6.6.2 - [
6.16 PCP l
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- .1 Attachment 4
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l 10 CFR 50.92 Evaluation ;
North Anna Units 1 and 2 1 .
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Virginia Electric and Power Com.pany F
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i Basis for No Sionificant Hazards Determination j The proposed change does not involve a significant hazards consideration as defined
- in 10 CFR 50.92 because operation of North Anna Units 1 and 2 in accordance with p this change would not:
(1) involve a significant' increase in the probability or consequence of an accident previously evaluated. _.This change does not alter.the conditions l or assumptions of any accident analysis.
(2) create the possibility of a new or different kind of accident from any accident previously identified. This change does not alter the conditions or L assumptions of any accident analysis. This is'not an actual hardware change.
(3) involve a significant reduction in a' margin of safety. This change does not alter the conditions or assumptions of any accident analysis, it is not an actual hardware change.
- Therefore, pursuant to 10 CFR 50.92, based on the above considerations, it has been '
determined that this change does not involve a significant hazards consideration, t
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.i Attachment 5
.i Offsite Dose Calculation Manual- i o
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Virginia Electric and Power Company I h
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