ML19261B979
| ML19261B979 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 03/06/1979 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML19261B978 | List: |
| References | |
| NUDOCS 7903090236 | |
| Download: ML19261B979 (76) | |
Text
.
RADIOLOGICAL EFFLUEllT TEClitlICAL SPECIFICATIONS NORTil ANNA POWER STATI0ft Attachment B to serial #402/071178, March 6,1979 790300023S
INDEX -
1 i;Offsite Dose Calculation Manual....... ............................ 1-5A i.
Ii 1:
li
- Continuous Monitors................................................ 1-5A l'
II I
i e
s 11 i
l l
l t
1 1
1 l
1 l.
1 i
t NORTH ANNA - UNIT 1 la
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMINTS SECTION Pace 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 Axial Flux Difference.......................... 3/4 2-1 3/4.2.2 Heat Flux Hot Channel Factor............ ...... ,/4 2-5 3/4.2.3 Nuclear Enthalpy Hot Channel Factor............ 3/4 2-9 3/4.2.4 Quadrant Power Tilt Ratio....... .............. 3/4 2-12 3/4.2.5 DNB Parameters.......... ...................... 3/4 2-14 3/4.2.6 Axial Power Distribution.. ........ ........... 3/4 2-16 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION............ 3/4 3-1 3/4-3 2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION.............................. 3/L 3-15 3/4.3 3 MONITORING INSTRUMENTATION Radiation Monitoring........................... 3/4 3-35 Movable Incore Detectors....................... 3/4 3-39 Seismic Instrumentation........................ 3/4 3-40 Meteorological Instrumentation................. 3/4 3-43 Auxiliary Shutdown Panel Moni toring Instrumen-tation............... ....................... 3/4 3-46 Post-Accident Instrumentation.................. 3/4 3-49 Fire Detection Instrumentation................. 3/4 3-52 Axial Power D i st ri but ion Moni toring System. . . . . 3/4 3-54 Radioactive Liquid Effluent Instrumentation.... 3/4 3-56 Radioactive Gaseous Effluents Inst umentation. 3/4 3-61 l 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS No rma l Ope ra t i on . . . . . . . . . . . . . ...... .......... 3/4 4-1 Isolated Loop.................................. 3/4 4-4 Isolated Loop Startup.......................... 3/4 4-5 NORTH ANNA - UNIT I IV
INDEX LIMITING CONDITIONS FOR OPERAll0N AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.9.10 WATER LEVEL-REACTOR VESSEL....................... 3/4 9-10 3/4.9.11 SPENT FUEL PIT WATER LEVEL.... .................. 3/4 9-11 3/4.9.12 F'J E L BU I LD I N G V ENT I LAT I O N SY ST EM. . . . . . . . . . . . . . . . . 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 RE ACTO R C OO LANT L00 P S . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 10-4 3/4.10.5 POSITION INDICATOR CHANNELS-SHUTDOWN............. 3/4 10-5 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS................. ............... 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS................................ 3/4 si-7 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITt . LNG PR0 GRAM............................... 3/4 12-1 3/4.12.2 LAND USE CENSUS.................................. 3/4 12-10 3/4.12.3 QUALITY ASSURANCE PR0 GRAM........................ 3/4 12-li X
. NORTH ANNA - UNIT 1
INDE, BASES 3/4.11 RADICACTIVE EFFLUENTS 3/4.11.1 LiqulD EFFLUENTS... ............... ............. B 3/4 11-1 3/4.11.2 GASEOUS EFFLUENTS................................. B 3/4 11-2 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PR0 GRAM................................ B 3/4 12-1 3.4.12.2 LAND USE CENSUS................................... B 3/4 12-1 3/4.12.3 QUAL I TY AS S U RANC E P R0G RAM . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 12-1 NORTH ANNA - UNIT 1 XVI-A
DEFINITIONS l{ l.0 Il
'l0FFSITEDOSECALCULATIONMANUAL(ODCM) i 1.27 An 0FFSITE DOSE CALCULATION MANUAL (ODCM) shall be a manual contain-I. ing the methodology and parameters to ba used in the calculation of off-l'si te doses due to radioactive gaseous and liquid ef fluents and in the cal-l culation of gaseous and liquid ef fluent monitoring instrumentation alarm /
trip setpoints consistent with the applicable LCO's contained in these ilTechnicalSpecifications.
. CONTINUOUS MONITORS I
1.28 As applied to in place radiation monitors and related flow indi-cators does not prevent the devices from being periodically taken out of service fer calibration or maintenance for periods not to exceed four
{ hours.
1
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i 1
NORTH ANNA - UNIT I l-5A
TABLE 1.2 FREQUENCY NOTATION NOTATION FREQUENCY S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D At least once pec ?4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
W At least once per 7 days.
M At least once per 31 days.
Q At least once per 92 days.
SA At least once per 184 days.
R At least once per 18 months.
S/U Prior to each reactor startup.
P Completed prior to each release.
N.A. Not applicable.
NORTH ANNA - UNIT 1 3/4 1-7
INSTRUMENTATION RADI0 ACTIVE Ll0Ul0 EFFLUENT INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3 3 9 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3 11.1.1 are not exceeded. The setpoints shall be determined in accordance with
- m. :thodology described in the ODCM.
APPLICABILITY: As shown in Table 3.3-12.
ACTION:
- a. With a radioactive liquid effluent monitoring instrumentation channel alarn/ trip setpoint less conservative than a value which will ensure that the limits of 3.11.1.1 are met, imme-diately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel in-operable.
- b. With one or more radioactive liquid effluent monitoring in-strumentation channels inoperable, take the ACTION shown in Table 3.3-12.
- c. The provisions of Specifications 3 0.3 and 3 0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3 3 9.1 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION, AND CHANNEL FUNCTIONAL TEST operations during the MODES and at the f requencies shown in Table 4.3-8.
4.3.3 9.2 Auditable records of setpoints and setpoint calculations shall be maintained to ensure that the linits of Specificatloas 3.11.1.1 are net.
NORTH ANNA - UNIT 1 3/4 3-56
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- .- N NORTH ANNA - UNIT 1 3/4 3-57
TABLE 3 3-12 (Continued)
TABLE NOTATION ACTION 23 W*tb the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may be resumed for up to 14 days, provided that prior to initiating a release:
- 1. Ar least two independent samples are analyzed in accordance with Specification 4.11.1.1. 3, a nd ;
- 2. At least two technically qualified members of the racility Staff independently verify the release rate calculations and discharge valving; Otherwise, suspend release of radioactive effluents via this pa t hwa y .
ACTION 24 With the numbers of channels OPERABLE lesc than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 14 days provided that at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> grab samples are collected and analyzed for gross radioactivity at a lower limit of detection of at least 10 7 pCi/ml, or by gamma isotopic analysis.
NORTH ANNA - UNIT 1 3/4 3-58
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TABLE 4.3-8 (Continued)
TABLE NOTATION
- Durina radioactive releases via this pathway.
(1) - The CHANNEL FUNCTIONAL TEST shall demor. strate that automatic isolation of this pathway occurs if levels exceed the setpoint.
Control room alarm annunciation occurs if any of the following conditions exist:
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Instrument controls not set in operate mode.
(2) - The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Instrument controls not set in operate mode.
(3) - The CHANNEL CALIBRATION shall include the use of a known radioactive source (s) positior.ed in a reproducible geometry with respect to the sensor whose effect on the system was established at the time of the PRIMARY CALIBRATION.
definition PRIMARY CAllBRATION is the determination of the electronic system accuracy when the detector is exposed in a known geometry to radiation from sources emitting beta and gamma radiation with fluences and energies in the ranges anticipated to be measured by the channel during normal operation. Sources should be traceable to the National Bureau of Standards.
(4) - CHANNEL CHECK shall consist of verifying indication of flow during periods of releasc. CHANNEL CHECK shall be made at least once daily on any day on which continuous, periodic, or batch releases are made.
NORTH ANNA - UNIT 1 3/4 3-60
INSTRUMENTATION RADIOACTIVE GASEOUS PROCESS AND EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3 3.3.10 The radioactive gaseous process and ef fluent monitoring instru-mentation channels shown in Table 3 3-13 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded. The setpoints shall be determined in accordance with methodology described in the ODCM.
APPLICABILITY: As shown in Table 3 3-13 ACTION:
- a. Wi th a radioactive gaseous process or ef fluent monitoring in-strumentation channel alarm / trip setpoint less conservative than a value which will ensure that the limits of 3 11.2.1 are met, declare the unannel i nope rab l e .
- b. With one or more radioactive gaseous process or effluent monitoring instrumentation channels inoperable, take the ACTION shown in Table 3 3-13
- c. The provisions of Specifications 3 0 3 and 3 0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.10.1 Each radioactive gaseous process or effluent monitoring instru-mentation channel shail be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CAllBRATION, and CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies shown in Table 4.3- 9 4.3.3 10.2 Audi table records of setpoints and setooint calculations shall be maintained to ensure shut the limits of Specifications 3.11 1 1 are met.
NORTH ANNA - UNIT 1 3/4 3-61
TABLE 3.3-13 5
RADIOACTIVE GASEOUS EFFLUEtiT tt0NITORING lilSTRUMENTAT g
? MINIMUM
{ , INSTRUMENT CilANNELS OPERABLE APPLICABILITY PARAMETER ACT10fl C
E 1. Process Vent System
-s
- a. Noble Gas Activity Monitor I Radioactivity Rate 27 Measurement
- b. Particulate Sampler i N/A 28
- c. Effluent System Flow Rate I System Flow Rate 26 Measuring Device Measurement d.
y Sampler Flow Rate Measuring I Sampler Flow Rate 26 g Device Measurement
- 2. Condenser Air Elector Gross Activity Monitor .
1 -
Radioactiviry Rate 27 Measurement
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TABLE 3 3 13 (Continued)
ACTION 26 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirements, effluent releases via this pathway may continue for up to 28 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ACTION 27 With the number of channels OPERABLE less chan required by the Minimum Channel s OPERABLE requi rement , effl uent releases via this pathway may continue for up to 28 days provided grab sam-ples are taken at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and these samples are analyzed for gross activity or gamma isotopic analysis within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 28 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 28 days, provided samples are continuously collected with auxiliary sampling equipment for periods not greater than seven (7) days.
NORTH ANNA - UNIT 1 3/4 3-64
TABLE 4.3-9 5
g RADI0 ACTIVE GASEOUS EFFLUENI MONITORING INSTRUMENTATION SURVElLLANCE REQUIREMENTS, z
& CNANNEL E CilANilEL CNANNEL FUNCTIONAL
( INSTRUMENT CllECK Call BRAT I Ori TEST E 1. Process Vent System G
- a. Noble Gas Activity Monitor De R(3) Q(1)
- b. Particulate Sampler De N/A N/A
- c. System Effluent Flow Rate D*(4) R Q Monitor
- d. Sampler Flow Rate lion i t o r D ."; R N/A T
- 2. Condenser Air Ejector De R(3) Q(1)
Gross Activity Monitor
- TABLE 4.3-9 (Continued) 5 3; RADIDACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS z
g CHANNEL g CHANNEL CHANNEL FUNCTIONAL INSTRUMENT CHECK CAllBRATION TEST E
- 3 Vent-Vent System H
- a. Noble Gas Activity Monitor DA R(3) Q(2)
- b. Particulate Sampler Da N/A N/A
- c. System Effluent Flow Rate Measurement Device Da(4) R Q s
- d. Sampler Flow Rate j'w Measurement Device De R N/A
TABLE 4.3-9 (continued)
TABLE NOTATION
- - During radioactive releases via this pathway.
(I) With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may be resumed for up to 14 days, provided that prior to initiating' a release :
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Instrument controls not set in opera te mode.
(2) - The CHANNEL FUNCTIONAL TEST shall be demonstrate that control room alarm annunciation occurs if any of the following conditions exist:
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Instrument controls not set in operate mode.
(3) - The CHANNEL CAllBRATION shall include the use of a known radioactive source (s) positioned in a reproducible geometry with respect to the sensor whose effect on the system was established at the time of the primary calibration.
DEFINITION PRIMARY CAllBRATION is the determination of the electronic system accuracy when the detector is exposed in a known geometry to radia-tion from sources emitting beta and gamma radiation with fluences and energies in the ranges anticipated to be measured by the channel during normal opera t ion. Sourcas should be traceable to the National Bureau of Standards.
(g) _ CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once daily on any day on which continuous, periodic, or batch releases are made.
NORTH ANNA - UNIT 1 3/4 3-67
3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATIJN 3.11.1.1 The concentration of radioactive material released in liquid waste ef fluent from the site to unrestric;.ed areas (see Figure 3 12-1) shall not exceed the concentrations specified in 10 CFR 20, Appendix B, Table ll, Column 2 for radionuclides other than dissolved or entrained noble gases. For each dissolvediar entrained ngble gas, the concentration shall be limited to 4 x 10-5 uCi/ml.
APPLICABILITY: At all times.
ACTION:
- a. With the concentration of radioactive material released from the site to unrestricted areas exceeding the above limits, immediately restore concentration v.ithin the above limits and provide prompt notification to the Commissic pursuant to Speci ficat ion 6.9.1. 8.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQU IREMENTS 4.11.1.1.1 The instantaneous concentration of radioactive material in liquid effluents released from the site shall be continuously monitored in accordance with Table 3 3-12.
4.11.1.1.2 The liquid effluent continuous monitors having provisions for automatic termination of liquid releases, as listed in Table 3 3-12, shall be used to limit the concentration of radioactive material released at anytime from the site to unrestricted areas to the values given in Speci-fication 3.11.1.1.
4.11.1.l.3 The radioactivity content of each batch of radioactive liquid waste to be discharged shall be determined prior to release by sampling and analysis in accordance wi th Table 4.11-1.
4.11.1.1.4 Post-release analyses of samples from batch releases shall be performed in accordance wi th Table 4.11-1.
NORTH ANNA - UNIT I 3/4 11-1
SURVEILLAtlCE REQUIREMEtiTS (Continued) i L.11.1.1.5 The radioactivity concentration of lic;u'ds discharged from i co.icinuous release points shall be determined by collection and analysis j
, of samples in accordance with Table 4.11-1.
ll Il NORTH ANilA - UNIT I 3/4 11-2
TABLE 4.11-1 RADIOACTIVE LIO.UID WASTE SAMPLING AND ANALYSIS PROGRAM
- Lower Limit of Detection Sampi ng M n mum Type of Activity (LLD)
Liquid Release Type Frequency Analysis Analysis (uti/mi)a Frequency P P A. Batch Waste Re- Each batch Each Batch PrincipafGamma 5 x 10 7 b lease Tanks Emitters 1-131 1 x 10-P One Batch /M M Dissolved and I x 10 5 Entrained Gases P H-3 1 x 10 5 Each Batch M Composite' Gross a 1 x 10-P .
Each Batch Q Sr-39, Sr-90 5 x 10 0 I Composite c d
B. Continuous PrincipagGamma PlantCont)nuous ,
5x 10 p Releases '
y; d Emitters l-131 1 x 10-M Grab Sample M Dissolved and Entrained Gases 1 x 10 5 d H-3 1 x 10 0 Cont.inuous M d
Composite Gross a 1 x 10 7 d
Continuous Q d Composite Sr-89, Sr-90 5 x 10 3 NORTH ANNA - UNIT 1 3/4 11-3
TABLE 4.11-1 (Continued)
TABLE NOTATION
- a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability ith 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical sepa ra t i on) .
LLD =
4.66 s b E -
V
- 2.22 x 106 . y . exp(- Aat) where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume) s is the standard deviation of the background counting rate b
or of the counting rate of a blank sample as appropriate (as counts per minute)
E is the counting efficiency (as counts per transformation)
V is the sample size (in units of mass or volume) 2.22 x 10 is the number of transformation per minute per microcurie Y is the fractional radiochemical yield (when applicable)
A is the radioactive decay constant for the particular radionuclide at is the elapsed time between sample collection (or end of the sample collection period) and time of counting The value of s used in the calculation of the LLD for a detec-b tion system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on en unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the back-ground shall include the typical contributions of other radio-nuclides normally present in the samples (e.g., potassium-40 in milk samples).
It should be recognized that the LLD is defined as an a, priori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement.
NORTH ANNA - UNIT 1 3/4 11-3A
TABLE 4.1 -1 (Continued)
TABLE NOTATION
- b. For certain radionuclides with low gamma yield or low energies, or for certain radionuclide mixtures, i t may not be possible to measure radio-nuclides in concentrations near the LLD. Under these circumstances, the LLD may be increased Inversely proportionally to the magnitude of the gamma yield (i .e. , 5 x 10 7/l, where ! is the photon abundance expressed as a decimal traction), but in no case shall the LLD, as calculated in this manner for a specific radionuclide, be greater than 10%
of the MPC value specified in 10CFR20, Appendix B, Table 11, Column 2.
- c. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is repre-sentative of the liquids released.
- d. To be representative of the quantities and concentrations of radio-active materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream.
Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representa-tive of the effluent release,
- e. A batch release is the discharge of liquid wastes of a discrete volume,
- f. A continuous release is the discharge of liquid wastes of a non-discrete volume; e.g., from a volume er system that has an input flow during the continuous release.
- g. The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Mn-54, Fe-59, Co-58, co-60, 2n-65, Mo-99, ts-134, Cs-137, Ce-141, and Ce-144.
This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level. When unusual ci rcumstances resul t in LLD's higher than required, the reasons shall be documented in the semiannual effluent report.
NORTH ANNA - UNIT 1 3/4 11-4
iRADl0 ACTIVE EFFLUENTS
' LIQUID EFFLUEllTS DOSE LIMITING CONDITION FOR OPERATION
,3 11.1.2 The dose or dose commitment per reactor to an individual from
' radioactive materials in liquid effluents released to unrestricted areas (see Figure 3 12-1) shall be limited during any calendar quarter to $_ l.5
, mrem to the total body and to 5. 5 mrem to any organ.
I t
APPLICABILITY: At all times.
ACTION:
- a. With the calculated dose from the release of radioactive materials
, in liquid effluents exceeding any of the above limits, prepare j and submit to the Commission within 30 days, pursuant to Speci-1 fication 6.9.2, a Special Report which identifies the cause(s)
I for exceeding the limit (s) and defines the corrective actions to be taken.
l
- b. The provisions of Specifications 3 0 3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS
- 4.11.1.2.1 Dose Calculations. Cumulative dose contributions from liquid effluents shall be determined in accordance with the Offsite Dose Calcula-tien Manual (00CM) at least once per 31 days.
i i
NORTH ANNA - UNIT 1 3/4 11-5
RADI0 ACTIVE EFFLUENTS LIQUID WASTE TREATMENT LIMITING CONDITION F01; OPERATION 3 11.1 3 The appropriate subsystems of the Liquid Radwaste Treatment System shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected dose due to liquid effluent releases to unrestricted areas (see Figure 3.12-1) when averaged over 31 days would exceed 0.25 mrem to the total body or 0.8 mrem to any organ.
APPLICABILITY: At all times.
ACTION:
- a. With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information:
- 1. ldentification of equipment or subsystems not OPERABLE and the reason for Inoperability.
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE status.
3 Summary description of action (s) taken to prevent to recur-rence.
- b. The provisions of Specification 3 0 3 and 3.0.4 are not applic-able.
SURVEILLANCE REQUIREMENTS 4.11.1.3 1 Doses due to liquid releases to unrestricted areas shall be projected at least once per 31 days.
4.11.1.3.2 The appropriate liquid radwaste subsystems shall be demon-strated OPERABLE at least once per 92 days unless the appropriate liquid radwaste subsystem has been utilized to process radioactive liquid effluents during the previous 92 days.
NORTH ANNA - UNIT 1 3/4 11-6
RADICACTIVE EFFLUENTS 3/4.11.2 GASE0US EFFLUENTS DOSE RATE LIMITING CONDITION F0h OPERATION 3 11.2.1 The instantaneous dose rate in the unrestricted areas (see Figure 3.12-1) due to radioactive materials released in gaseous ef fluents from the site shall be limited to the following values:
- a. The dose rate limi t for noble gases shall be < 500 mrem /yr to the total body and < 3000 mrem /yr to the skin, and
- b. The dose rate limit for all radioiodines and for all radioactive materials in particulate form and radionuclides other than noble gases with half lives greater than 8 days shall be < 1500 mrem /yr to any organ.
APPLICABILITY: At all times.
ACfl0N:
- a. With the dose rate (s) exceeding the above limits, immediately decrease the release rate to comply with the limit (s) given in Speci fication 3 11.2.1 and provide prompt notification to the Commission pursuant to Specification 6.9.1.C.
- b. The provisions of Specifications 3.0.3 and 3 0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The instantaneous release rate of noble gases in gaseous effluents shall be determined by continuous monitoring of the release points given in Table 3 3-13 The instantaneous release rate shall be used to determine the offsite dose rate. l 4.11.2.1.2 The noble gas effluent continuous monitors having provisions for the automatic termination of gaseous releases, as listed in Table 3.3-i3 shall be used to limit offsite doses within the values established in Specification 3.11.2.1 when monitor setpoint values are exceeded.
4.11.2.1.3 The release rate of radioactive materials, other than noble gases, in gaseous effluents shall be determined by obtaining representative samples and performing analyses in accordancewith the sampling and analysis program, specified in Table 4.11-2.
4.11.2.1.4 The dose rate in unrestricted areas, due to radioactive materi-als other than nobel gases released in gaseous effluents, shall be deter-mined to be within the required limits by using the results of the sampling and analysis program, speci fied in Table 4.11-2, in accordance with the methodology of the ODCM.
NORTH ANNA - UNIT 1 3/4 11-7
TABLE 4.11-2 RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANAlvSIS PP.0 GRAM z
@ itinimum Lower Limit of j Sampling Analysis Type of Detection (LLD)
> Gaseous Release Type Frequency Frequency Activity Analysis (uCi/ml)" ,
5
> P P A. Each Tank Each Tank Principal Ganuna Emi t ters g -4b Process Vent System 1x 10 E Grab Sample
-6
- H-3 i x 10 P P B. Containment Vent Each Purge Each Purge Principal Gamma Emitters g -4b 1 x 10 System Grab Sample
-6 11 - 3 1 x 10 w - 41'
) C. Ventilation H '" .i Principal Ganuna Emi t ters 9 1 x 10
_ Vent System Grab
~
- 0. Air Ejectors ll-3 -6 1x 10 Al1 Release Typa,s Continuous I -12 E. W'I I-131 1x 10 as listed in A, B Charcoal C above. 5.mple -10 I-133 1x 10 f d Continuous W lx 10 )
Particulate Principal Gaurna Emi t ters J Sample (I-131, Others)
-11 I
M Gross alpha 1x 10 Continuous Composite Particulate Sample Continuous f Sr-89, Sr-90 -33 Comhosite 1x 10 Particulate Sample
TABLE 4.11-2 (Continued)
TABLE NOTATION
- a. The lower limit of detection (LLD) is defined in Table Notation a. of Table 4.11-1 of Specification 4.l!.l.l.'
- b. For certain radionuclides with low gamma yield or low energies, or for certain radionuclide mixtures, it may not be possible to measure radio-
'nuclides in concentrations near the LLD. Under t.hese circumstances, the LLD may bc increased inversely proportionally to the magnitude of the gamma yicld (i.e., 1x 10 "fl, where I is the photon abundance expressed as a decimal fraction), but in no case shall the LLD, as calculated in this manner for a specific radionuclide, be greater than 104 of the MPC value specified in 10CFR20, Appendix B, Table I I , Col umn 1
- c. reserved
- d. An dyses sha!! also be parformed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for 7 days fdl':owing each shutdown, startup, or similar operational occurrence which could lead to significant increases or decreases in radio-iocine releases. Samplers shall also be changed and analyzed at the intervals in Specii. cations 3 11.2.1 and 3.11.2.3 When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLD's may be increased by a factor of 10.
- e. Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust.
- f. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.11.2.1, 3.11. 2. 2, and 3 11.2.3 .
I
- g. The principal gamma emitters for which the LLD specification will l apply are exclusively the following radionuclides: Kr-87, Kr-88, !
Xe2 133, Xe-133m, Xe-135, and Xe '38 for gaseous er.issions and Mn-54, i
'r e-53, Co-58, co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 :
l for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are j measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for th:t nuclide. When ungsual circumstances result in LLD's higher than required, the reasons shall be documented in the semi-annual effluent report.
' ORTH AMMA - UNIT 1 3/h 11-9
!RADI0 ACTIVE EFFLUENTS l
'! DOSE, N0BLE GASES I
l LIMITING LONDITION FOR OPERATION 3.11.2.2 The air dose per reactor in unrestricted areas (see Figure 3 12-1) due to noble gases released in gaseous effluents shall be limited to the following during any calendar quarter, to < 5 mrad for gamma radiation and
< 10 mrad for beta radiation.
APPLICABILITY: At all times.
ACTION:
- a. With the calculated air dose from radioactive noble gases in
, gaseous effluents exceeding any of the above limits, prepare l and submit to the Commission within 30 days, pursuant to Speci-ficatien 6.9.2, a Special Report which identifies the cause(s) fcr exceeding the limit (s) and defines the corrective actions to be taken.
i
- b. The provisions of Speci fications 3.0 3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.2.1 Dose Calculations. Cumulative dose contributions for the total time period shall be determined in accordance with the Offsite Dose Calculation Manual (0DCM) at least once every 31 days.
NORTH ANNA - UNIT 1 3/4 11-10
,RADICACTIVE EFFLUENTS
,, DOSE, RADl010 DINES. RADICACTIVE MATERIAL IN PARTICULATE FORM. AND ll PAD 10NUCLIDES OTHER THAN NOBLE GASES i
flLIMITINGCONDIT!ONFOROPERATION I t I
,3..l.2.3 The dose per reactor to an individual from radiciodines, radio-
> active materials in particulate form, and radionuclides other than noble i gases with half-lives greater than 8 days in gaseous effluents released to
!! unrestricted areas (see Figure 3.12-1) shall be limited during any calendar quarte r to < 7. 5 mrem.
l l APPLICABILITY: At all times.
I!
! ACTION:
I
- a. With the calculated d,se from the release of radiciodines, radioactive materials in particulate form, or radionuclides other than noble gases in gaseous effluents exceeding any of l.
.; the above limits, prepare and submit to the Conmission with i in 30 days, pursuant to Specification 6.9.2, a 'special Report l which identifies the cause(s) for exceeding the limit ar.d l
defines the corrective actions to be taken.
i b. The provisions of Specifications 3.0 3 and 3.0.4 are not l applicable.
SURVEILLANCE REQUIREMENTS I
gj4.11.2 3.1 Dose Calculations. Cunulative dose contributions for the total ,
li time period shall be determined in accordance wi th the ODCM at least once
jevery 31 days.
i h
I l!
l!
'i e
il
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e li
, NORTH ANNA - UNIT I 3/4 11-11 I
i
RADI0 ACTIVE EFFLUENTS GSSEGUS RA0 WASTE TREATMENT LIMITING CONDITION FOR OPERATION ,
3 11.2.4 The appropriate subsystems of the Gaseous Radwaste Tr eatment ,
System shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases to unrestricted areas (see Figure 3.12-1) when averaged over 31 days excaeds 0.8 mrad for gamma radiation, 1.6 mrad for beta radiation, or 1.2 mreri to any organ.
APPLICABILITY: At all times.
ACTION:
- a. With gaseous waste being discharged for more than 31 days without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information:
- 1. Identification of equipment of subsystems not OPERABLE and the reason for inoperability.
- 2. Action (s) taken to restore the inoperable equipment to OPERABLE STATUS. -
3 Summary description of action (s) taken to prevent a re- a currence.
- b. The provisions of Specification 3 0 3 and 3 0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases to unrestricted areas shall be projected at least once per 31 days in accordance wi th the FDCfl.
NORTH ANNA - UNIT 1 3/4 11-12
RADICACTIVE EFFLUENTS GAS SiCRAGE TANKS LIMIT!NG CONDITION FOR OPERATION 3.11.2 5 The quantity of radioactivity contained in each gas storage tank shall be limited to < 25,000 curies noble gases (considered as xe-133).
APPLICABILITY: 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 /> either reduce the tank contents to within the limit or provide prompt notification to the Commission pursuant to Speci ficat ion 6.9.1. 3.. The written followup report shall include a description of activities planned and/or taken to reduca the tank contents to within the above limit.
- b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.5 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limi t at least monthly when radioactive materials are being added to the tank.
I NORTH AtlNA - UNIT 1 3/4 11-13
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be con-ducted as specified in Table 3.12-1. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazard-ous conditions, seasoaal unavailability, or malfunction of automatic sampling equipment.
APPLICABILITY: At all times.
ACTION:
- a. All deviations from the sampling schedule shall Se described in the Annual Radiological Environmental Operating Report (Section 6.9.1.10).
- b. With the level of radioactivity in an environmental sampling medium at one or more of the locations specified in Table 3 12-1 exceeding the limits of Table 6.9-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter, a Special Report which includes an evaluation of any release condi tions, environmental factors or other aspects which caused the limits of Table 6.9-2 to be exceeded. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Anaual Radiological Environmental Operating Report.
- c. The provisions of Specifications 3 0 3 and 3 0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12.1.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3 12-1 from the locations shown on Figure 3.12-1 and Figure 3 12-2 and shall be analyzed pursuant to the requirements of Table 3.12-1.
The initially specified monitoring program will be effective for at least the first three years of commercial operation. Following this period, program changes may be initiated based on operational exoeri-ence.
NORTH ANNA - UMIT l *3/4 12-1
TABLE 3.12-1 NORTil ANNA POWER STATION OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 2
S
$ EXPOSURE PATNWAY SAMPLE LOCATION AND/0R SAMPLING AND TYPE AND FREQUENCY 3; AND/0R SAMPLE HAP NUMBER DESIGN /. TION COLLECTION FREQUENCV 0F ANALYSIS 5
[ AIRBORNE
[ Particulates Site or site boundary: 1,21, Continuous sampler Weekly gross beta on 22, 23 (2/3 running time each filter, quarterly Communities: 3,5,7 cycle), changes gamma isotopic on each Control: 24 weekly location composite, Sr-89-90 on second Radiciodine 3,21,23,24 quarter composite, yh I-131 on radioiodine weekly.
7 w
Soil 1,3,4,5,6,7,21,22,23,24 Once per 3 years Gamma isotopic on each, Sr-89-90 on 1,21,22, ,
23, 24 (on collect ion)
DIRECT I,3,4,5,6,7,21,22,$b,24 Quarterly Gamma dose quarterly WATERBORNE Reservoir: 9 Monthly Gamma isotopic radio-Discharge: 8 iodine" 11-3 quarterly composite, Sr-89-90 second quarter composite North Anna River: li Quarterly Gamma isotopic, N-3 on Ground (well): l A'g collection, Sr-89-90 second quarter sample
TABLE 3.12-1 (Continued)
NORTil ANilA POWER STATION r OPERATI0tlAL RADIOLOGICAL EllVIRONMENTAL MONITORitlG PROGRAM S
~4 E EXPOS'RE PATilWAY SAMPLE LOCATIOP AND/0R SAMPLING At1D TYPE AND FREQUENCY E Fh/0R SAittLE MAP NUMBER DES 1GNATION COLLECT 10H FREQUENCY OF ANALYS1S e
E AQUATIC Reservoir: 9 Serniann ua l l y Gmunia isotopic on
-l Sediment Discharge: 8 col let.t ion , Sr 89-90
- North Anna River: 11 annually Shoreline Vicinity o'- 9 4 INGESTION
" railk Hea res t Dairies: 12, 13, lie Monthly" Radioindinc#'", Canana C' isotopic monthly, Sr
., 89-90 quarterly Hon-dairy activity Calculated dose Radiolodine '" , Ganuna dependent i sot opi c Sr 89-90 Fish Reservoir: 9 Annually, near Ganuna isotopic (Bass, or sunfish) Discharge: 8 beginning of season or crappie and catfish)
Green Leafy 21, 23 Annually during Gansna isotopic on vegetation, collection cultivated or harvest' weeds. Naturally occurring
TABLE 3.12-1 (C.atinued) 5 NORTil ANNA POWER STATION Q OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM x
$ EXPOSURE PATHWAY SAMPLE LOCATl0N AND/0R SAMPLING AND TYPE AND FREQUENCY
, AND/0R SAMPLE MAP HUMBER DESIGNATION COLLECTION FREQUENCY OF ANALYSIS E
-i
- a. Once per 31 days I and 2 mrem thyroid isodose lines will be calculated usino the previous month's release data based on the cow milk-child pathway. Should a dairy be located within the 1 mrem isodose line the y sampling and analysis frequency for radioiodine will be modi fied to semimonthly for tfw month following the month for which the calculation was made. A similar sampling program will be for tae 2 mrem isodine r line except on a weekly frequency.
- b. Updates of the current year's annual accumulated calculated thyroid 15 mrem isodose lines based on the goat-milk-child and the cow milk-child pathway will be done at least once per 31 days. Should the isodose extend beyond the site boundary, a survey to locate goats or cows within the isodose line will be carried out within 30 days. Should goats or cows be observed, ef forts to obtain samples from the owners of the animals will be put forth. I f samples are unattainable, a sampling program similar to "a" above will be initiated. if samples are unobtainable, the annual report will document such and include the calculated doses.
- c. Update- ./ an annual 15 mrem isod se line (using release data ani maximum organ dose in each of the 16 s e c t o r.- based on the grass-catti -beef man pathway will be done at least once per 31 days. Should the idodose line extend beyond the si'e boundary, sampling and analyses will be modified to monthly for the current year.
- d. Samples will be taken from the Envi ron.nental Laboratory well .
- c. Radioiodine analyses will be done by chemical separation.
e T
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u4
642 R ADIOLOGICAL
\ -
/ ENVIRONMENTAL
@ ORANGE f SAMPLING STATIONS Y
[ l
2
,/
. FIGURE 3.12 - 2 SAMPLE LOCATIONS-U
- . , x ~-
6 42
/
4 204
, , ,/
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L l ' h s
o y, [,// ,, Oi 9 (s3 ROS HOADS 42 - '4 x g pg ,N.') ER ST ATION
\
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, s 614 652 - i x- 60s
- se ,_, .
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652 r 6(i SC ALE IN MIL E S 7Dl
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TABLE 4.12-1 LOWER LIMIT!i 0F DETECTION BY HIGH RESOLUTION Ge(Li) GAMMA SPECTROSCOPY ENVIRONiiENTAL SAMPLES Water (1 l i te r) Soil & Vegetation Filters Nuclide pC1/1 (400 cm) pCi/am pCi/ total filter Be 8E+01 2E-01 2E+0i K 2E+02 SE-01 SE+01 Cr 8E+01 2E-01 8E+01 54 2E-02 2 Mn 8 S8 Co 8 2E-02 2 59 4E-02 Fe lE+01 3 0
Co 8 2E-02 2 Zr 95 IE+01 4E-02 3 03 8 2E-02 2 Ru Ru 8E+01 2E-01 8E+01 31 2 1 10 3E-02 34 2E-02 2 Cs 9 37 2E-02 2 Cs 9 0
Ba 3E+01 8E-02 6 La 2E+01 4E-02 2E+01 Ce 2E+01 4E-02 3 Ce 8E+01 2E-01 2E+01 Ra 6E+01 1E-01 lE+01 Th 1E+01 2E-02 1E+01 NORTH ANNA - UNIT 1 3/4 12-7
TABLE 4.12-2 LOWER LIMITS OF DETECTION L.L.D. 5 Sampled Volume Sample Analysis Reporting Units Recuired
- 1. Airborne Particulate .3 3 125 m3 Gross Alpha Gross Beta 25x 10_3pCi/n 10 pCi/m3 7.6 x Ge(LI) y-isotopic See Table 4.12-1
- 2. Airborne lodine 125 m3 Charcoal Cartridge 1-131 2.4 x 102pCi/m3 3 Direct Radiation TLD Environmental Badge 2mR + 2mR
- 4. Milk 4 liters Sr-90 0.8 pCi/L l-131 by Chemical Separation 0 5 pCi/t Total Calcium Ge(Li) y-isotopic (Cs-137) See Table 4.12-1 Cs-137 Chemical Separation 3 pC1/t 5 Well Water 2 liters Gross Alpha 0 5 pCi/t Gross Beta 0.5 pCi/l Tritium (Gas count) 100 pCi/l Ge(li) y-isotopic See Table 4.12-1
- 6. Surface Water 2 liters Gross Beta 0 5 pCi/2 Tritium (gas count) 100 pCi/t Ge(Li) y-isotopic See Table 4.12-1 7 Fish: Flesh (2) 1 Kg Gross Beta plus K-40 0.1 pCi/gm wet Ge(Li) y-isotopic See Table 4.12-1 Sr-89 0.8 pCi/gm*
Sr-90 0.5 pCi/gm*
- 8. Vegetation Samples (2) 1 Kg A. Corn Ge(Li) y-isotopic See Table 4.12-1 Sr-90 0.5 pCi/gm*
- 8. Leaf Vegetation (2) 1 Kg Ge(Li) See Table 4.12-1 Sr-89 0.8 pCi/gm*
Sr-90 0.5 pCi/gm*
C. Food / Garden Crops (e.g. (2) 1 Kg Ge(Li) Lettuce) See Table 4.12-1 Sr-89 0.8 pCi/gm*
Sr-90 0.5 pCi/gm*
NORTH ANNA - UNIT 1 3/4 12-8
TABLE 4.12-2 (Contin;ed)
LOWER LIMITS OF DETECTION L.L.D. s Sampled Volume Sample Analysis Reporting Units Required D. Terrestrial Vegetation i Kg Cc(LI) See Table 4.12-1 E. Aquatic Vegetation Ge(LI) y-isotopic See Table 4.-l Sr-89 0.8 pCi/gm a Sr-90 0 5 pCi/gm*
9 Soil i Kg Ge(LI) y-isotopic See Table 4.12-1
- Detection in limits as stated are per gram of ashed material . The actual detection limits in pCi/gm (wet) will vary by a factor of 10-100, depending on the wet versus ash weight factor.
NORTH ANNA - UNIT I 3/4 12-9
RADIOLOGICAL ENVIRONMEllTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify the location of the nearest milk anical, the nearest residence and the nearest garden
- of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles.
APPLICABILITY: At all times.
ACTION:
- a. With a land use census identifying a location (s) which yields a calculated dose or dose commitment areater than the present controling location, the new location shall replace the sampling location which has the lowest calculated dose or dose comnitment.
- b. The provisions of Specifications 3.0.3 and 3 0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12.2.1 The land use census shall be conducted at least once per 12 months between the dates of June 1 and October 1, by door-to-door survey, aerial survey, or by consulting local agriculture authorities.
- Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest D/Q in lieu of the garden census.
NORTH ANNA - UNIT 1 3/4 12- 10
RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12 3 QUALITY ASSURANCE PROGRAM LIMITING CONDITION FOR OPERATION 3.12 3 Analyses shall be performed on sample radioactive +aterials supplied as part of a Quality Assurance Program which has been approved by NRC.
APPLICABILITY: At all times.
ACTION:
- a. With analyses not being performed as required above. report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operat'ng Report.
- b. The provisions _'f Specification 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.12.3 The results of analyses performed as part of the above required quality Assurance Program shall be included in the Annual Radiological Envi ronmental Operating Report.
NORTH ANNA - UNIT 1 3/4 12- 11
INSTRUMENTATION BASES 3/4.3.3 9 RADICACTIVE LIQUID EFFLUENT INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents, during actual or potential releases. The alarm / trip setpoints for these intruments shall be calculated in accordance with the ODCM to ensure that the alarn/ trip will occur prior to exceedina the limits of 10 CFR Part 20. The maintenance and use of this instrumentation is consistent with the requirements or General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
3/4.3 3.10 RADI0 ACTIVE GASEOUS EFFLUENT INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases. The alarn/ trip setpoints for these instruments shall be calculated in accordance with the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The maintenance and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50. j NORTH ANNA - UNIT I B 3/4 3-4
1;3/4.11 RADI0 ACTIVE EFFLUENTS ll ljBASES li i-LIOUID EFFLUENTS l3/4.11.1 3/4.11.1.1 CONC ENTRAT I ON i
i This specification is provided to ensure that the concentration of f' radioactive materials released in liquid waste effluents from the site to li unrestricted areas will be less than the cnneentration levels specified i in 10 CFR 20, Appendix B, Table 11. The concentration limit for noble
' gases is based upon the assumption that Xe-135 is the controlling
, radioisotope and its MPC in air (submersion) was converted to an
- equivalent concentration in water using the methods described in International Commission or Radiological Protection (ICRP) Publication
'2.
I l
! 3/4.11.1.2 DOSE This specification is provided to implement the requirements of ISections IV.A of Appendix 1, 10 CFR Part 50. The ACTION statements provided
' the required operating flexibili ty and at the same time implement the guides set forth in Section IV.A of Aopendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable". Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculations in the ODCM implement the requirements in Section Ill.A of Appendix 1 that conformance with the guides of Appendix I is to be shown by cal-culational methods based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977, and Regulatory Guide 1.113
" Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purposes of implementing Appendix 1," April 1977
'NUREG-0133 provides methods for dose calculations consistent with Regulatory l Guides 1.109and1.113 NORTH ANNA - UNIT 1 B 3/4 11-1
,,RADI0 ACTIVE EFFLUENTS I
BASES I.
!! This specification applies to the release of liquid efflents from
!!eachreactorat the site. For uni ts wi th shared radwaste treatment
!! systems, the liquid effluents f rom the shared system are proportioned
!' among the units sharing that sys tem.
l l The maintenance of the liquid radwaste treatment system ensures that l this system will be available for use whenever liquid effluents require
,jtreatment prior to release to the environment. The requi rement that the l appropriate portions of this system be us.,d when specified provides assur-ance that tFe releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This specification imple-ments the requirements of 10 CFR Part 50 36a, General Design Criterion 60 of Appendix A to 10 CFR Part 30 and the design objectives of Appendix I
,to 10 CFR Part 50. The specified limits governing the use of appropriate
,! portions of the liquid radwaste treatment system were specified as a sui table f raction of M.a guide set forth in Section ll.A of Appendix 1, 10 CFR Part 50, for ilquid ef fluents.
I 3/4.11.1.3 LIQUID WASTE TREATMENT t
! The maintenance of the liquid radwaste treatment system ensures that
- this system will be available for use whenever liquid effluents require
' treatment prior to release to the environment. The requirements that the lappropriateportionsofthissystembeusedwhenspecifiedprovidesassur-
!ance that Lne releases of radioactive materials in liquid effluents will
,be kept "as low as is reasonably achievable". This specification implements
, the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix jato 10CFR50anddesignobjectiveSection ll.D of Appendix I to 10 CFR 50.
l The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were speci fied as a sui table f raction of the guide set forth is Section ll . A of Appendix I, 10 CFR 50, for liquid l ef fl uents.
Il 3/4.I1.2 GASE0US EFFLUENTS j3/4.11.2.1 DOSE This specification is provided to ensure that the dose at any time
, at the exclusion area boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unres tricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Apendix B, Table !!. These limits provide reasonable assurance that radioactive material discharged j in gaseous effluents will not result in the exposure of an individual i in an unrestricted area ei ther wi thin or outside the exclusion boundary,
! to annual average concentrations exceeding the limits specified in Appendix B, Table 11 of 10 CFR Part 20 (10 CFR Part 20.106(a)). For NORTH ANNA - UNIT I B 3/4 11-2
l RADI0 ACTIVE EFFLUENTS l BASES
!lindividualswhomayat times be within the exclusion area boundary, t;
the occupancy of the individual will be sufficiently lav to compensate for any increase in the atmospheric diffusion factor above that for the ex-clusion area boundary. The specified release rate limits restrict, at
'all times, the corresponding gamma and beta dose rates above background l to an individual at or beyond the exclusion area boundary to 5. 500 l mren/ year to the total body or to 5. 3000 mren/ year to the skin. These irelease rate limits also restrict, at all times, the corresponding thyroid
,1 dose rate above background to an infant via the cow-milk-infant pathway i { to 5, 1500 mrem / year for the cow at the controlling location.
Il
! This specification applies to the release of gaseous effluents from ieach eactor at the site. For uni ts wi th shared radwaste treatment l systems, the gaseous ef fluent from the shared system are proportioned
' among the uni ts sharing that sys tem.
3/4.11.2.2 DOSE, N0BLE GASES This specification is provided to implement the requirements of Section IV.A of Appendix 1, 10 CFR Part 50. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV. A of Appendix ! assure that the releases of radio-active material in gaseous eff uents will be kept "as low as is reasonably
- achievable." The Surveillance Requirements implement the requirements in iSection Ill.A of Appendix I that conformance with the guides of Appendix !
is to be shown by calculational methods based on models and data such that the actual exposure of an individual through the appropriate path-ways is unlikely tu be substantially underestimated. The dose calcula-tions established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents will be consistent with the methodology provided in Regulatory Guide 1.109,
" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance wi th 10 CFR Part 50, ,
Appendix 1," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977 The ODCM equations provided for determining the air doses at the exclusion areas boundary will be based upon the historical average atmos-pheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111.
3/4.11.2 3 DOSE, RAD 1010 DINES, RADI0 ACTIVE MATERIAL IN PARTICULATE FORM
'AND RADIONUCLIDES OTHER THAN N0BLE GASES This specification is provided te implement the requirements of Section IV. A of Appendix 1,10 CFR Part 50. The ACTION statements provide the re-quired operating flexibility and at the same time implement the guides set NORTH ANNA - UNIT I B 3/4 11-3 b
,,RADICACTIVE EFFLUENTS il ll BASES
'i llforthinSection IV.A of Appendix ! to assure that the releases of radio-iactive materials in gaseous effluents will be kept "as low as is reasonably l l achievable." The ODCM calculational methods specified in the surveillance
'! requi rements implement the requirements in Section Ill.A of Appendix I
- that conformance with the guides of Appendix I be shown by calculational methods based on models and data such that the actual exposure of an lll individual through appropriate pathways is unlikely to be substantially I underestimated. The 00CM calculational methods for calculating the doses
!due to the actual release rates of the subject materials will be consistent i
I!withthemethodologyprovidedinRegulatoryGuide 1.109,Effluents Annual Dos.rs to Man from Routine Releases of Reactor " Calculating for theof Pur-
'lposeofEvaluatingCompliancewith10CFRPart 50, Appendix I," Revision 1, 40 ctober 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric iTransport and Dispersion of Gaseous Effluents in Routine Releases from
' Light-Water-Cooled Reactors," Revision 1, July 1977 These equations also
'j provide for determining the actual doses based upon the historical average latmospheric conditions. The release rate specifications for radiciodines, i! radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in tne unrestricted area. The pathways which are examined in the development of these calculations are: 1) individual inhalation of airborne radionuclides,
- 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, l
and 4) deposition on the ground with subsequent exposure of man.
' ;l 3 /4.11. 2. 4 GASEOUS WASTE TREATMENT ll The maintenance of the gaseous radwaste treatment system ensures that l the systems will be available for use whenever gaseous ef fluents require i treatraent prior to release to the envi ronment. The requirement that the l
- i appropriate portions of these systems be used when specified provides
. reasonable assurance that the releases of radio "tive material in gaseous leffluentswillbekept "as low as is reasonably achievable." This specifi-cation implements the requi rements of 10 CFR Part 50.36a, General Design i Criteriun oO of Appendix A to 10 CFR Part 50, and des ign objective Section }
l llD of Appendix ! to 10 CFR Part 50. The speci fied limi ts governing the I
use of appropriate portions of the systems were specified as a suitable fraction of the guide set forth in Section IV.A of Appendix 1, 10 CFR Part 50, for gaseous ef fluents.
3/4.11.2.5 GAS STORAGE TANKS I
l Restricting the quantity of radioactivity contained in each gas i
storage tank provides assurance that in the event of an uncontrolled
, NORTH ANNA - UNIT 1 B 3/4 11-4 l
i h
,R'AD10ACT!VE EFFLUCNTS
' BASES l release of the tanks co.ients, the resulting total body exposure to an Individual at the nearest exclusion area boun .ary will not exceed 0.5 rem. This is consistent with Standard Revifa Plan 15.7.1, " Waste Gas System Failure."
t
,I i
I NORTH ANNA - UNIT 1 B 3/4 11-5 1
!; 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING
!i
- jBASES l!
l 3 /4.12.1 MONITORING PROGRAM l!
i
^! The radiological monitoring program required by this specification
! in l those provides measurements exposure of radiation pathways and for thoseand of radioactive radionuclides materials which lead to the Ihighest potential radiation exposures of individuals resulting from
!thestationoperation. This monitoring program thereby supplements the
' radiological effluent monitoring program by verifying that the measur-
! able concentrations of radioactive materials and levels of radiation are
.inot higher than expected on the basis of the effluent measurements and
'lmode1ing of the envir.nmental exposure pathways.
1
! i 3/4.12.2 LAND USE CENSUS l
This specification is provided to ensure that changes in the use
' of unrestricted areas are identified and that modifications to the monitor '
l ing program are made if required by the results of this census. This l l census satisfies the requirements of Section IV.B.3 of Appendix I to 10 l l CFR Part 50. Restricting the census to gardens of greater than 500 square i j
lj feet provides assurance that significant exposure pathways via leafy ijvegetableswillbeidentifiedandmonitoredsinceagardenofthissize e is the minimum required to produce the quantity (26 kg/ year) of leafy l vegetables assumed in Regulatory Guide 1.109 for consumption by a l8; child. To determine this minimum garden size, the following assumptions jwereused, 1) that 20S; of the garden was used for growing broad leaf vegetation, (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/ square meter. !
43/4.12.3 QUALITY ASSURANCE PROGRAM j The requi rement for participation in a Quality Assurance program j is provided to ensure that independent _ Gecks on the precision and ;
accuracy of the me.surements of radioactive material in environmental
! sample matrices are performed as part of a quality assurance program for l environmental monitoring in order to demonstrate that the results are I reasonably valid.
i l
I NORTH ANNA - UNIT 1 B 3/4 12-1 1
ADMINISTRATIVE CONTROLS not specifically considered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition.
J. Exceeding the limits of 3.11.1.1, 3.11.2.1, and 3.11.2.6.
THIRTY-DAY WRITTEN REPORT 6,9.1.9 The types of events iisted below shall be the subject of written reports to the Director of the Regional Offico within 30 days of occurrence of the event. The writtea report shall include, as a minimum, a completed copy of the licensee event report form. Information pro-vided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.
- a. Reactor protection system or engineered safety feature instru-ment settings which are found to be less conservative than those established by the technical specifications but which do not prevent the ful fillment of the functional requirements of affected systems.
- b. Conditions leading to operation in a degraded mode permitted by a limiting condition for operation, or plant shutdown required by a limiting condition for operation.
- c. Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.
- d. Abnormal degradation of systems othar than those specified in item 6.9.1.8(c) above designed to contain radioactive material resulting from the fission orocess.
NORTH ANNA - UNIT I 6-18
ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 2!
6.9.1.10 Routine radiological environmental operating (Specification 3 12.1) reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The ini tial report shall be submitted prior to May I of the year following criticality.
6.9.1.11 The annual radiological environmental operating reports shall include summaries, interpretations and statistical evaluation of the results of the radiological enviror. mental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveil-lance reports and an assessment of the observed impacts of tne plant operation on the environment. The reports shall also include the results of the land use censuses required by Specification 3.12.2.
The annual radiological environmental operating reports shall include summarized and tabulated results in the format of Table 6.9-1 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.
1 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 2!
6.9.l.12 Routine radioactive ef fluen t release reports covering the operating of the unit during the previous 6 months of operation shall be submitted within 60 days af ter January I and July I of each year. The
- period of the first report shall begin with the date of initial criticality .
-3/ A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all uni ts 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 6-18A
ADitlNISTRATIVE CONTROLS SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT (Continued' ,
- a. This report shall include a summary of the results of analyses performed in accordance with the program of Table 4.11-1 and a summary of all releases of radioactive liquid efflents.
- b. This report shall include the quarterly summations of calculated dose contributions in TS 3.11.1.2, 3.11.2.2, 3.11.2.3
- c. This report shall include the summary of the results of analyses performed in accordance with 4.11.2.1.3, and a summary of all releases of radioactive gaseous effluents.
- d. This report shall include the following information for each type of solid waste shipped offsite during the report period:
- 1. container volume
- 2. total curie quantity (determined by measurement or estimate) 3 principal gamma radionuclides (determined by measure-ment or estimate).
- 4. type of waste (e.g , spent res in, compacted d ry was te ,
evaporator bottoms) 5 type of container (e.g. , LSA, Type A, Type B, Large Ouantity)
NORTH ANNA - UNIT 1 6-188
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!! ADMINISTRATIVE CONTROLS r.
,i lj6.91.13 The radioactive ef fluent release reports shall include a l; summary of the quantities of radioactive liquid and gasecas effluencs I: and solid waste released f rom tne unit as outlined in Regulator'/ Guide ll1.21," Measuring, Evaluating,andReportingRadioactivity in Solid I, Wastes and Releases of Raoloactiva Material in Liquid and Gaseous l; Ef fluents from Light-Water-Cooled Nucl? 3r P2nr Plants ," with data i
i summarized on a quarterly basis following the fornat of Aapendix B
((thereof.
The radioactive effluent release reports shall include a sumary of
,; the meteorological cond; tions during each qucrter wi th d ta summarized j;on a quarterly basis following the format of Appendix B of Regulatory [
- ~ Guide 1.21, Revision 1. June 1974 ;
i.
lTheradioactiveeffluent release report shall include the following l in fo rna t i on for all unplanned offsite releases of radioactive materials j in gaseous and liquid ef fluents: l
.i l ll a. A description of the e9ent and equipment involved. i li +
44 i, b. Cause(s) for the unplanned release. l
!! t
!! c. Actions taken to prevent recurrence. !
i l
- d. Consequereces of the unplanned release. l 1
.lThe radioactive effluent release reports shall include an assessment of l
'j radiation doses from the radiouctive liquid and gaseous effluents released from the unit during each calendar quarter according to the nethodologies {
,;of the 00CM. In addition, the unrestricted area bounda y maximun noble lj gas gamna air and beta air doses shall be evaluated. T1e reteorological j l conditions used in the Aopendix I Evaluation shall be used for deternining
!the gaseous pathway doses. The assessnent of radiation dcses shall be f t! perforned in accordance with the Offsite Oose Calculation Manual (CDCM).
iChanges to the ODCM shall be submi ttei to the NRC in the seniannual Ef fl uen t i;elease Report, i
f I
i l
1 NORTH ANNA - UNIT 1 6-18D
1ABLE 6.9-2
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Fe-59 4x 10 , ,g le Co-58 1x 10 3 3x lo b
h Co-60 3x 10 1x 10 '
Zn-65 3x 10 2 x 10 2
Z r- fib-95 4x 10 1-131 2 0.9 2 3 1x 10 Cs-134 30 10 1x 10 3 60 1x 10 3 Cs-137 50 20 2x 10 3 70 2x 10 3 Ba-LA-140 2x 10 3x 10 m+w me
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ADMINISTP.ATIVE CONTROLS 6.9.2. Special reports shall be submitted to the Director of the Reg-ulatory Operations Regional Office wi thin the time period specified for each report. These reports shall be submitted covering the activities identi fied below pursuant to the requirements of the applicable reference spec i fi cat ion :
- a. Inservice inspection Program Reviews shall be repcrted within 90 days of completion. Specification 4.4.10.1.
- b. ECCS Actuation shall be reported within 90 days of the oc-currence. The report shall describe the circumstances of the actuation and the total accumulated cycles to date. Spec-ification 3 5.2 and 3 5 3
- c. With Seismic Monitoring Instrumentation inoperable for more that 30 days, submit a soecial report within the next 10 aays outlining the cause of tr.e mal function and the plans for restoring the instrumentation to operable status. Spec-ification 3 3 3 3
- d. For all seismic events actuating a seismic monitoring instrument, submit a special report within 10 days describing the magnitude, frequency spect rum and resultant ef fects upon features important to safety. Specification 4.3.3.3.2.
- e. With Meteorological lastrumentation inoperable for more than 7 days, submit a special report within the next 10 days, outlining the cause of the mal function and the plans for restoring the instrumentation to operable status. Specifica-tion 3.3 3.4.
- f. '!i th the primary coolant specific activity > 1.0 uCi/ gram DOSE EQU Fv'ALENT l-131 or > 100/E uCi/ gram, a specific activity analysis shall be included in the REPORTA8LE OCCURRENCE report required pursuant to Specification 6.9.1.7 The information requested in Specification 3.4.8 shall also be included in that report.
- g. With sealed source or fission detector leakage tests revealing the presence of > 0.005 microcuries of removable contamination s t.ai t a special report on an annual basis outlining the corrective actions taken to prevent the spread of contamination.
Specification 4.7.11.1.3
- h. With the MTC more posit ve than 0 ak/k/ F submit a special report within the next 10 days describing the value of the measured MTC. the interim control rod withdrawal limits and the predicted averaga core burnup necessary for restoring the positive MTC to within its limit for the all rods withdrawn condition. Specifica-tior. 3 1.1.4.
- NORTH ANNA - UNIT 1 6-19
ADMINISTRATIVE CONTROLS
- i. 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 submit *ed within 10 days af ter detection and a detailed report submitted within 90 days af ter the completion of Specification 4.4.10.
J. For any abnormal degradation of the containment structure detection during the performance of Speci fication 4.6.1.6, <
an initial report shall be suomitted 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 correc*ive actions taken, shall be sub-mitted within 90 days after the completion of Specification 4.6.1.6.
- k. Inoperable Fire Detection Instrumentation, Specification 3.3.3.7
- 1. inoperable Fire Supression Systems, Specifications 3.7.14.1, 3.7.14.2, 3.7.14.3, 3.7.!4.4 and 3.7.14.5
- n. For the calculated dose from the release of radioactive material in effluents which exceed the limits of 3.11.1.2; 3.11.1.3; 3 11.2.2; 3.11.2 3; 3 11.2.4.
- n. When Action Levels of Table 6.9.2 are exceeded, as stated in Section 3 12.1.
6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:
- a. Records and logs of facility operation covering time interval at each power level.
- b. Records and logs of principal maintenance activities, in spections, repair and replacement of principal items of equip-ment related to nuclear safety.
- c. Each REPORTABLE OCCURRENCE submitted to the Commission.
- d. Records of surveillance activities, inspections and cali-brations required by these Technical Specifications.
NORTH ANNA - UNIT 1 6-20
ADMINISTRATIVE CONTROLS 6.10 RECORD RETENTION
- e. Records of Changes made to Operating Procedures.
- f. Records of radioactive shipments.
- g. Records of sealed source leak tests and results.
- h. Records of annual physical inventory of all sealed source material of record.
6.10.2 The fcilowing records shall be retained for the duration of the Facility Operating License:
(Begins on page 6-21)
NORTH ANNA - UNIT 1 A-20A
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TABLE OF CONTENTS PAGE 1.0 DEFINITIONS .......................................... 1-1 2.0 LIMITING CONDITIONS FOR OPERATION .................... 2-1 2.1 No n - Ra di ol o gi c a l . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-1 2.2 Reserved........................................ 2-1 3.0 ENVIRONMENTAL SURVEILLANCE ........................... 3-1 3.1 Non radiol ogi cal Surveill an ce . . . . . . . . . . . . . . . . . . . . 3-1 3.1.1 Abi o ti c - Aq ua ti c . . . . . . . . . . . . . . . . . . . . . . . . 3-1 3.1.1.1 Wa t e r Q ua l i ty . . . . . . . . . . . . . . . . . . . . . . . . . . 3-1 3 .1.1. 2 Th e rma l Me a s u re me n t s . . . . . . . . . . . . . . . . . . . 3- 3 3.1. 2 B i o ti c Aq ua ti c . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-9 3.1. 2 .1 General Ecol o gi cal Survey . . . . . . . . . . . . . . 3-9 3.1. 2 . 2 Impi n ge men t o f Orga ni s ms . . . . . . . . . . . . . . . 3-11 3.1.2.3 Entrainment o f Ichthyoplankton . . . . . . . . . 3-12 3.1. 3 Abi o ti c - Terres tri al . . . . . . . . . . . . . . . . . . . . 3-13 3.1. 3.1 Transmission Line Rights-of-Way Herbicide Management ......................... 3-13 3.1.3.2 Transmission Line Right-of-Way trosion Control Inspection .. . . . ........... 3-14 3.1. 4 Ons i te Me teorol o gy Moni to ri n g . . . . . . . . . . . . 3-15 3.2 Reser"ed ........................................ 3-16 i
TABLE OF CONTENTS (Cont'd)
Pace 4.0 SPECIAL SURVEILLANCE AND STUDY ACTIVITIES................... 4-1 4.1 Chemical Inventory..................................... 4-1 4.2 .-getation Studies..................................... 4-2 5.0 ADMINISTRATIVE CONTR0LS............................ ........ 5-1 5.1 Responsibility......................................... 5-1 5.2 Organization........................................... 5-1 5.3 Review and Audit...................................... 5-1
- 5. 3 .1 Station Nuclear Safety and Operating Committee (SNS0C)....................................... 5-1 5.3.1.1 Function.................................... 5-1
- 5. 3.1. 2 Responsibility.............................. 5-1 5 . 3 .1. 3 Authority................................... 5-3 5.3.1.4 Records..................................... 5-3 5.3.2 Supervisor, Quality Assurance, Operation and Maintenance...................................... 5-4 5.3.2.1 Function.................................... 5-4 5.3.2.2 Audits.... ................................. 5-4 5.3.2.3 Records..................................... 54 5.3.3 System Nuclear Safety and Operating Committee (SyNS0C)........................ .............. 5-4 5.3.3.1 Function.................................... 5-4 5.3.3.2 Review.................................... . 54 5.3.3.3 Responsibility.............................. 5-5 5.3.3.4 Authority................................... 5-5 5.3.3.5 Records................................. ... 5-5 5.4 State and Federal Permits and Certificates............. 5-5 5.5 Procedures........ .................................... 5-5 5.5.1 Written Procedures.. ........................... 5-5 5.5.2 Operating Procedures........ . ......... ..... 5-5 5.5.3 Reserved .......................................
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TABLE OF CONTENTS (Cont'd)
PAGE 5.5.4 Procedures for Environmental Surveillance - 5-6 Nonradiological ......................................
5.5.5 Qua l i ty Assurance of Program Resul ts . . . . . . . . . . . . . . . . . . . . 5-6 5.5.6 Changes in Procedures, Station Design or Operation ...................................... ..... 5-6 5.5.7 Consistency with Ini tially Approved Programs . . . . . . . . _ . . . 5-7 5.6 Station Reporting Regt *ements .................................. 5-7 5.6.1 Routine Reports ......................................... 5-7 5 . 6 .1.1 Annual Environmental Operating Report . ....... 5-7 5.6.2 Nonroutine Reports ...................................... 5-9
- 5. 6 . 2 .1 Nonroutine Non-Radiological Enviror. mental Operating Report ........................... 5-9 5.6.3 Changes in Environmental Technical Specifications . . . .. .. 5-12 5.6.4 Changes in Permits and Cer ti fica tions . . . . . . . . . . . . . . . . . . . 5-12 5.7 R e c o rd s Re n t e n ti o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-12
1.0 DEFINITIONS Accuracy: Refers to the deviation of a result obtainea by a parti-cular method from the value accepted as true.
Aerial Renote Sensing: The reasurement or acquisition from aircraft or spacecraf t of information on some property of an object or pheno-renon by a recording device that is not in physical or intimate con-tact with the object of phenomenon under study. The technique employs such devices as the camera, radio frequency receivers, and radar systers.
Annually: Annusily is once per calendar year at intervals of twelve calendar months, plus or minus 30 days.
Combined Available Chlorine: Chlorine existing in water in chemical combination witn ammonia or organic nitrogen compounds.
Condenser Discharge Structure: Located at the beginning of canal "A".
Effluent water from Units Nos. I and 2 exits through this structure to canal "A".
Daily Average Concentration: Daily average concentra*. ion means the arithmetic average of all daily determinations of concentration made during a calendar nonth. Daily determinations of concentration using a corposite sample shall be the concentration of the composite sample.
When grab samples are used, the daily determination of concentration shall be the arithnetic average of all the samples collected during that calendar year.
Daily Maximum Concentration: Daily maximum concentration reans the m.aximum concentration recorded for any calendar day.
Free Available Chlorine: Chlorine existing in water as hypochlorus acid and nypocnlarite icns.
Grab Sanale: A grab sarole is an individual sample collected in less that fi f teen minutes.
Ground Truth or Grour.d Data Surveys : Supporting data collected on the ground and information derived therefrom, as an aid to the interpretation of remotely-recorded servey, such as aerial imagery, etc. Generally, this should be perforred cuncurrently with the airborne surveys.
He rbici des : Chemicals that kill plants or inhibit their normal growth.
Infrared, chotograchic: Pertaining to or designating the portion of the electromagnetic spectrum with wavelengths just beyond the red end of the visible spectrum; generally defined as from 0.7 to about 1.0 am, or the useful limits of film sensitivities.
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Lake Anna: The impounded waters of the North Anna River near the Station, excluding the Waste Heat Treatment Facility.
Manner of Herbicide Apolication:
- a. Basal injection in which the selected individual trees achieve herbicide injections beneath the bark;
- b. Basal application in which individual plants are treated with pellets or sprays applied to soi' at the base of the plant;
- c. Selective foliar spray (spot treatments or directed spray) in which individual plants are sprayed with ground-based equipment;
- d. Broadcast apolication in which herbicide is distributed either as pellets or spray uniformly over the entire predetermined area of land;
- e. Aerial application in which entire segmente of the corridor are treated primarily by broadcast applications employing various types of aircraft.
Mon thl y: Monthly is once during every calendar month at intervals of 30 dr.ys plus or minus three days.
Multispectral or Maltiband Photographs _: A color picture produced by assigning a color to a particular spectral band.
Normal Operation: Operation of the station at greater than 5% of rated thermal power in other than a safety emergency situatior.
NPDES Permit: NPDES Permit is the National Pollutant Discharge Elimination System Permit No. VA 0052451 issued by the Commonwealth of Virginia to Virginia Electric and Power Company. This permit authorizes VEPCO to discharge, from the North Anna Power Station, controlled waste water into the waters of the Common-weal th of Virginia.
Quarterly: Quarterly is once during each successive three month period of the calendar year, counting from January 1, at intervals of 13 weeks plus or minus 9 days.
Protected Areas: Ecological areas designated by the Staff to receive special mitigative actions such as selected vegetative communites bordering rivers or strea- which are not to receive herbicidal applications, etc. (This definition is for environmental considerations only and does not relate to plant security considerations).
Scale: The ratio of a distance on a photograph or map to its corresponding distance on the ground.
Semi-Mon thl y : Semi-monthly is twice during each calendar month at intervals of 15 days plus or minus 2 days.
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Spectral Band: A width, generally expressed in wavelength or frequency of a particular portion of the electromagnetic spectrum. A given sensor (e.g.,
radiometer detector or camera film) is designed to measure or be sensitive to energy received from that part of the spectrum.
Station and Unit: 5tation refers to North Anna Power Station, Units Nos. i and
- 2. Unit refers only to Unit No.1 or Unit No. 2.
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2.0 LIMITIrlG C0iiDITIC::S FOR OPERATION -
2 .1 fJon-Radiological - None 2.2 Reserved (Pages 2-2 through 2-17 are deleted) 2-1
observations in a form consistent with National Weather Service procedures. Summaries of all data and observations shall be available to the NRC upon request. If the outage of any meteoro-logical instrument (s) exceeds seven consecutive days, the total outage time, the dates of outage, the cause of the outage, and instrument (s) involved shall be reported within 30 days in accord-ance with Section 5.6.2.1.
Any modification to the meteorological monitoring program as described above, or planned alterations of the area in the vicinity of the meteorological tower (s) that would interfere with the measurement of meteorological conditions representative of the site, will require written approval in accordance with Section 5.6.3.
Bases The collection of meteorological data at the plant site will provide information which will be used to assess the actual impact of the plant cooling system on the atmospheric environment of the site area.
A meteorological data collection program as described above is necessary to meet the requirements of 10 CFR 51.
3.2 Reserved (Pages 3-17 through 3-25 are deleted) 3-16
5.0 ADMINISTRATIVE CONTROLS Administrative controls established below are deemed adequate to implement the Environmental Technical Specifications which provide continuing protection to the environment.
5.1 Responsibility The responsibility for implementing the Environmental Technical Specifications is assigned to the Director of Nuclear Operations at the corporate level and to the Station Manager at the station level .
The Superintendent - Operations shall be responsible for ensuring that the station is operated in accordance with the Limitin' Conditions of Operation. The Executive Manager of Environmental Sr - l vices shall be responsible for providing services which will fulfill the nonradiological environmental surveillance requirements.
5.2 Orcanization The relationship between the Production Operations !*
Department and the Environmental Services Department is shown in Figure 5.2-1.
5.3 Review and Audit 5.3.1 Station Nuclear Safety and Oceratinc Committee (SNSCC) 5.3.1.1 Function The SNSOC, as described in Section 6.5.1 of Appendix A of this license, shall function to advise the Station Manager on matters related to the environmental impact of the station. When the SNSCC is exercising its resconsibility for non-radiological aspects of the ETS, the Station Biologist or his alternate shall be consulted. l*
5.3.1.? Resoonsibilitv The SNSOC shall be responsible for:
- a. Coordination of the Environmental Technical Specifications with the Safety Technical Specifications (Appendix A) to avoid con-flicts and maintain consistency.
- b. Review of changes to the Environmental Tecnnical Specifications and the evaluation of the environmental impact of the change.
,) r'"'icusly cequested in December 26,1978 'etter, serial number 652 5 -1
5.3.3.3 Responsibility The SyNS0C has the responsibility for ensuring that the station is operated in accordance with the requirements of this license and applicaole NRC regulations.
5.3.3.4 Au thori ty The SyNSOC shall report to and advise the Vice President - Power Supply and Production Operations on those areas relating to the environ-mental impact of the station.
5.3.3.5 Records The SyNSCC shall maintain written minutes of each meeting and a copy shall be provided to the committee members, and Vice President - Power Supply and Production Operations on those areas relating to the environmental impact of the station.
5.4 State and Federal Permits and Certificates The licensee shall comply with the provisions of the permits and certificates issued by the Commonwealth of Virginia to North Anna Power Station under the provisions of Section 401 and 402 of the Federal Water Pollution Control Act, as amended.
5.5 Procedures 5.5.1 Written Procedures Detailed written procedures, including applicable checklists and instructions, shall be prepared and followed for all activities involved in carrying out the Environmental Technical Soecifications as defined in Sections 5.5.2 and 5.5.4, below. Procedures shall include sampling, data recording and storage, instrument calibration, measure- l ments and analyses, and actions to be taken when limits are approached or exceeded. Testing frequency of any alarm shall be included. These frecuencies shall be determined from experience with similar instru-ments in similar environments and from manufacturer's technical manuals.
5.5.2 00eratina Procedures Plant standard operating procedures shall include provisions, in addition to the procedures specified in Section 5.5.1, to ensure that all plant systems and components are operated in compliance with the Limiting Conditions of Operations established as part of the Environ
- mental Technical Specifications.
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5.5.3 Reserved 5.5.4 Procedures for Environmental Surveillance - Nonradiological All sampling programs for plankton, benthos, nekton, etc., will be conducted in accordance with accepted scientific procedures and in a manner amenable to statistical treatment. The accepted scientific procedures will be reviewed by the Environmental Services Department as a service to the station.
5.5.5 Ouality Assurance of Prooram Results The procedures document shall provide for assurance of the quality of program results, including analytical measurements. This portion of the procedures document shall document the program in policy directives, designate a responsible organization or individuals, include purchased services (e.g., contractual lab or other contract services), include audits by licensee personnel, and include procedures for revising programs, systems to identify and correct deficiencies, investigate anomalous or suspect results, and review and evaluate program results and reports.
5.5.6 Changes in Procedures, Station Design or Ooeration Changes in procedures, station design or operation may be made subject to conditions described below, provided such changes are approved by the SNSOC (Review and Audit responsibility per Section 5.3).
- a. The licensee may (1) make changes in the station design and operation as described in the FES, FES Addendum and the Environ-mental Report, (2) make changes in the procedures described in the document developed in accordance with Subsection 5.5, and (3) conduct tests and experiments not described in the document developed in accordance with Subsection 5.5, without prior Commis-sion approval, unless the proposed change, test or experiment involves a change in the objectives of the ETS, an unreviewed environmental question of substantive ir?act, or affects the requirements of Subsection 5.5.7 of tresa ETS.
- b. A proposed change, test, or experiment shall be ddemed to involve an unreviewed environmental question (1) if the probability of magnitude of environmental impact may be increased; or (2) if a possibility for a substantive environmental impact of a different type than any evaluated previously in the FES or FES Addendum may be created.
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e the NRC Region II Office (with a copy to the Director, Office of Nuclear Reactor Regulation) as a separate document by May 1 of each year. The period of the first report shall begin with the date of initial criticality of Unit No.1. The report shall include summaries, interpretations, and statistical evaluation of the results of the nonradiological environmental surveillance activities (Section 3.1),
the environmental monitoring programs required by limiting conditions for operation (Section 2) and the special surveillance and study activities (Section 4) for the report period, including a comparison with preoperational studies, operational controls (as appropriate),
and previous environmental monitoring reports and an assessment of the observed impacts of the plant operation on the environcent. If harmful effects or evidence of irreversible damage are suggested by the monitoring programs, the licensee shall provide a more detailed analysis of the data and a proposed course of action to alleviate the problem.
5.6.2 Nonroutine Reports 5.6.2.1 Nonroutine Non-Radiological Environmental Operatina Report A report shall be submitted in the event that (a) a limiting ondition for operation is exceeded (as specified in Section 2, "Limitirig Condi-tions for Operation"), (b) a report level is reached (as specified in Section 3, " Environmental Surveillance"), or (c) an unusual or impor-tant event occurs that causes a significant environemtnal impact, that affects potential environmental impact from station operation, or that has high public or potential public interest concerning environmental impact from station operation. Also, if, during the operating life of the Station, evidence of irreversible damage is detected, the applicant will provide to the Staff an analysis of the problem and a proposed course of acticn to alleviate the problem. Reports shall be submitted under one of the report schedules described below.
- a. Promot Report. Tho;e events specified as prompt record occurrences shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone, uelegraph and/or facsimile transmission to the Director of the NRC Region II offices.
This report will be supplemented by a written report to be submitted within 30 days.
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- b. Thirty-day Reoorts. Non-routine events not requiring a prompt report shall be reported to the NRC within 30 days of the occurrence or within the time limit specified by the reporting requirements of the corresponding permit or certification issued pursuant to section 401 or 402 of PL 92-500, whichever time duraticn following the non-routine event shall result in the earlier submittal .
Written 30-day reports will be submitted to che following addresses:
(1) Region II, Office of Inspection and Enforcement, USNRC, Atlanta, Georgia (2 copies)
(2) Oirector, Office of Inspection and Enforcement, USNRC, Washington, D.C. (20 copies)
(3) Director, Office of Management Information and Prcgram Control, USNRC, Washington, D.C. (2 copies)
(4) Director, Office of Nuclear Reactor Regulation, USNRC, Washington, D.C. (1 copy)
- c. Content of Non-Routine Reports. Written 30-day reports and, to the extent possible, the preliminary telephone, telegraph, or facsimile reports shall (a) describe, analyze, and evaluate the occurrence, including extent and magnitude of the imoact, (b) describe the cause of the occurrence, and (c) indicate the corrective action (including any significant changes made in procedures) taken to preclude repetition of the occurrence and to prevent similar occurrences involving similar components or systems.
The significance of an unusual or apparently important event with ragard to envi crmental impact may not be obvious or fully appre-ciated at the time of occurrence. In such cases, the NRC shall be informed promptly of changes in the licensee's assessment of the significance of the event and a corrected report shall be submitted as expeditiously as possible.
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5.6.3 Changes in Environmental Technical Soecifications A report shall be made to the NRC prior to implementation of a change in plant design, in plant operation, or in procedures described in Section 5.5 if the change would have a significant effect on the environment or involves an environmental matter or question not previously reviewed and evaluated by the NRC. The report shall include a description and evaluation of the change and a supporting benefit-cost analysis.
Request for changes in environmental technical specifications shall be submitted to the Director, Division of Operating Reactors, for review and authorization. The request shall include an evaluation of the environmental impact of the proposed changes and a supporting benefit-cost analysis.
5.6.4 Changes in Permits and Certifications Changes to required Federal and State permits and certificates which pertain to the requirements of these ETS shall be reported to the NRC within 30 days. In the event that the licensee initiates or becomes aware of a r equest for changes to any of the water quality requirements, limits or values stipulated in any permit or certification issued pursuant to Section 401 or 402 of PL 92-500 which is also the subject of an ETS reporting requirement, NRC shall be notified concurrently with the authorizing agency. The notifica-tion to the NRC shall include an evaluation of the environmental impact of the revised requirement, limit or value being sought.
5 . ,' Records Retention Records and logs relative to the following areas shall be made and retained for the life of the station:
- a. Records and drawings detailing plant design changes and modifica-tions made to systems and equipment as described in Section 5.6.3.
- b. Reports from environmental monitoring, surveillance, and special surveillance and study activities required by these Environmental Technical Specifications.
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