ML20132G419
| ML20132G419 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 06/18/1985 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19283F593 | List: |
| References | |
| NUDOCS 8508050022 | |
| Download: ML20132G419 (15) | |
Text
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UNITED STATES g
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g NUCLEAR REGULATORY COMMISSION 5
- j WASHINGTON. D. C. 20555
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LOUISIANA POWER AND LIGHT COMPANY DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 1 License No. NPF-38 1.
The Nucle,ar Regulatory Connission (the Connission) has found that:
A.
The application for amendment, dated May 14, 1985, by Louisiana Power and Light Company (licensee), complies with standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, the provisions of Act, and the rules and regulations of the Connission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Connission's regulations; D.
The issuance of this amendment will not be inimical to the connon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Connission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-38 is hereby amended to read as follows:
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(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 1, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in this license.
LPAL shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of May 16, 1985.
FOR THE NUCLEAR REGULATORY COMMISSION eorge W Knig ton ' hief g
Licensing Branch No. 3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
JUN 181985
_= ___= ___.
JUN 181985 4 1 ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 1 TO FACILITY OPERATING LICENSE NO. NPF-38 DOCKET NO. 50-382 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Also to be replaced are the following overleaf pages to the amended pages.
Amendment Pages Overleaf Pages 3/4 3-56 3/4 3-55 3/4 3-58 3/4 3-57 3/4 3-59 3/4 3-60 3/4 11-3 t
3/4 11-3a 3/4 11-4 3/4 11-Sa 3/4 11-5 3/4 11-6 (reissued withou+ change) e 4
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1 7
l i
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i 1
j INSTRUMENTATION RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION f
l LIMITING CONDITION FOR OPERATION I
t 3.3.3.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm / trip setpoints set to i
ensure that the Ifmits of Specification 3.11.1.1 are not exceeded.
The alarm /
l trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL l
(ODCM).
APPLICABILITY:
At all times.
l ACTION:
i l
a.
With radioactive liquid effluent monitoring instrumentation channel i
alarm / trip setpoint less conservative than required by the above l
Specification, immediately suspend the release of radioactive liquid l
effluents monitored by the affected channel, or declare the channel l
b.
With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown j
in Table 3.3-12. Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION or, explain in the l
next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.8, why this inoperability was not corrected
]
within the time specified.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
I j
SURVE!LLANCE REQUIREMENTS l
l l
4.3.3.10 Each radioactive liquid effluent monitoring instrumentation channel
[
shall be demonstrated OPERA 8LE by performance of the CHANNEL CHECK, SOURCE
[
j CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the
[
frequencies shown in Table 4.3 8.
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l ilk i
i Q. M1 E
M bN
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TA8LE 3.3-12 E
1 3
RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION l
3 g
MINIMUM CHANNELS INSTRtM NT OPERABLE ACTION cz U
1.
RADI0 ACTIVITY MONITORS PROVIDING ALARM ANO w
AUTOMATIC TERMINATION OF RELEASE a.
Boric Acid Condensate Discharge 1
28 b.
Waste, Waste Condensate and Laundry Discharge 1
28 c.
Dry Cooling Tower Sumps 1/ sump 29 d.
Turbine Building Industrial Waste Sump 1
29 e.
Circulating Water Discharge (Blowdown Heat Exchanger and Auxiliary Component Cooling Water Pumps)#
1 29 2.
C0KTINUOUS COMPOSITE SAMPLERS a.
Steam Generator Blowdown Effluent Line 1
29 3.
FLOW RATE MEASUREENT DEVICES a.
Beric Acid Condensate Discharge 1
30 b.
Maste, Waste Condensate and Laundry Discharge 1
30 t
c.
Turbine Building Industrial Waste Sump
- N.A.
N.A.
S d.
Dry Cooling Tower Sumps
- N.A.
N.A.
e.
Circulating Water Discharge * (Blowdown and Blowdown Heat l
Exchanger and Auxiliary Component Cooling Water Pumps)
N.A.
N.A.
t'
- Automatic termination of blowdown discharge only l
TABLE 3.3-12 (Continued)
TABLE NOTATIONS
- Pump performance curves generated in place shair be used to estimate flow.
ACTION STATEMENTS 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 14 days provided that prior to initiating a release:
a.
At least two independent samples are analyzed in accordance with Specification 4.11.1.1.1, and b.
At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 29 -
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 30 days provided grab samples are analyzed for radioactivity at a lower limit of detection of at least 10-7 microcurie /mL.
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 microcurie / gram DOSE EQUIVALENT I-131.
b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 micro-curie / gram DOSE EQUIVALENT I-131.
ACTION 30 -
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 30 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 /> during actual releases.
Pump performance curves generated in place may be used to estimate flow.
WATERFORD - UNIT 3 3/4 3-57
TABLE 4.3-8 E
M RADIDACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS m
o CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST Ea 1.
RADI0 ACTIVITY MONITORS PROVIDING ALARMS AND AUTOMATIC TERMINATION w
OF RELEASE a.
Boric Acid Condensate Discharge P
P R(3)
Q(1) b.
Waste, Waste Condensate and Laundry P
P R(3)
Q(1)
Discharge c.
Dry Cooling Tower Sumps D
M R(3)
Q(5) d.
Turbine Building Industrial Waste Sump D
M R(3)
Q(5) e.
Circulating water Discharge (Blowdown Heat Exchanger and w2 Auxiligry Component Cooling Water Pumps)
D M
R(3)
Q(5)
~
o 2.
CONTINUOUS COMPOSITE SAMPLERS a.
Steam Generator Blowdown Effluent Line D(6)
N.A.
R Q
3.
FLOW RATE MEASUREMENT DEVICES a.
Boric Acid Condensate Discharge D(4)
N.A.
R Q
b.
Waste, Waste Condensate and Laundry D(4)
N.A.
R Q
Discharge c.
Turbine Building Ir.dustrial Waste Sump N.A.
N.A.
N.A.
N.A.
g d.
Dry Cooling Tcwr Sumps N.A.
N.A.
N.A.
N.A.
e.
Circulating Water Discharge 3
(Blowdown and Blowdown Heat l
Exchangers and Auxiliary 2o Component Cooling Water Pumps)
N.A.
M.A.
N.A.
N.A.
- Automatic termination of Blowdown discharge only l
TABLE 4.3-8 (Continued)
TABLE NOTATION (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm / trip setpoint.
2.
Circuit failure.
3.
Instrument indicates a downscale failure.
(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm setpoint.
2.
Circuit failure.
(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards or using standards that have been obtained from suppliers that partf Ipate in measurement assurance activities with NBS.
These standards r ill permit calibrating the system for over its intended range of energy and measurement range.
For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.
(4) CHANNEL CHECK shall consist of verifying indication of flow during periods of release.
CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.
(5) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway occurs if the instrument indicates measured levels above the alarm / trip setpoint and that control room alarm annunciation occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm set.
2.
Circuit failure.
3.
Instrument controls not set in operate mode.
(6) CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous releases are made to the Circulating Water System or Waterford 3 waste pond.
WATERFORD - UNIT 3 3/4 3-59 Amendment No. 1
INSTRUMENTATION l
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION
/
LIMITING CONDITION FOR OPERATION 3.3.3.11 The radioactive gaseous effluent monitoring instrumentation channels l
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 alarm /
trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the 00CM.
APPLICABILITY:
As shown in Table 3.3-13.
i ACTION:
a.
With a radioactive gaseous effluent monitoring instrumentation j
channel alarm / trip setpoint less conservative than required by the above Specification, imrr-diately suspend the release of radioactive 1
gaseous effluents monitored by the affected channel, or declare the channel, inoperable, b.
With less than the minimum number of radioactive gaseous effluent j
monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13.
Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION or, explain,in the next Semiannual Radioactive Effluent Release Report, purs'uant to l
Specification 6.9.1.8, why this inoperability was not corrected within the time specified.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable, SURVEILLANCE REQUIREMENTS 4.3.3.11 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated CIERABLE by performance of the CHANNEL CHECK, SOURCE i
CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-9.
)
4 WATERf0RD - UNIT 3 3/4 3-60
TABLE 4.11-1 (Continued)
~
LOWER LIMIT MINIMUM 0FDETEC{ ION LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD)
TYPE FREQUENCY FREQUENCY ANALYSIS (pCi/mL)
B. Continuous W
W Principal Gamma 5x10 7 Releases **#
Grab Sample Emitters l
e
M M
Dissolved and 1x10 s
- 2. Dry Cooling Grab Sample Entrained Gases Tower (Gamma Emitters)
Sump #1**j-
- 3. Dry Cooling W
M H-3 1x10 5 d
Tower Grab Sample Composite i
Sump #2**9 Gross Alpha 1x10 7
- 4. Circulating W
Q Sr-89, Sr-90 5x10 8 Water i d
Grab Sample Composite Discharge-Fe-55 1x10 5 Steam Gene-rator Blow-down HX
- 5. Auxiliary Component Cooling Wateri Pumps
- When release from this source is continuous in nature.
WATERFORD - UNIT 3 3/4 11-3 Amendment No. 1
TABLE 4.11-1 (Continued)
LOWER LIMIT MINIMUM OFDETECfION LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD)
TYPE FREQUENCY FREQUENCY ANALYSIS (pCi/mL)
B. Continuous W
W Principal Gamma 5x10 7 Releases *'I Continuous Composite Emitters k
d c
6.
Steam Generator I-131 1x10 8 Blowdown 3
Discharge 'I M
M Dissolved and 1x10 s Grab Sample Entrained Gases (Gamma Emitters)
W M
H-3 1x10.s k
d Continuous Composite Gross Alpha 1x10 7 W
0 Sr-89, Sr-90 5x10 s k
d Continuous Composite Fe-55 1x10 8 WATERFORD - UNIT 3 3/4 11-3a Amendment No. 1
~
TABLE 4.11-1 (Continued)
TABLE ' NOTATION aThe LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiochemical separation:
4.66 sb E
V 2.22 x 106 Y
exp (-Aat)
Where:
LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, s
is the standard deviation of the background counting rate or of the h
c5unting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, -[
(
V is the sample size in units of mass or volume, 2.22 x'106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and at for plant effluents is the elapsed time between the midpoint of sample collection and the time of counting.
Typical values of E, V, Y, and at should be used in the calculation.
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 an a posteriori (after the fact) limit for a particular measurement.
bA batch release is the discharge of liquid wastes of a discrete volume.
Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in the ODCM to assure representative sampling.
k WATERFORD - UNIT 3 3/4 11-4
TABLE 4.11-1 (Continued)
TABLE NOTATIONS cThe principal gamma emitters for which the LLD specification applies include the following radionuclides:
Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144.
This list does not mean that only these nuclides are to be considered.
Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.8.
dA 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 that is representative of the liquids released.
'A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g.,- from a volume of a system that has an input flow during the
., continuous release.
Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.
Ifthecontentsofthefilterflushtankortheregenerativewasketank 9
contain detectable radioactivity, no discharges from these tanks shall be made to the UNRESTRICTED AREA and the contents of these tanks shall be directed to the liquid radwaste treatment system.
hTurbine Building Industrial Waste Sump (TBIWS)
The TBIWS shall be required to be sampled and analyzed in accordance with this table if any of the following conditions exist:
(1) Primary to secondary leakage is occurring; or, (2) Activity is present in the secondary system as indicated by either the SGB monitors or secondary sampling and analysis; or, (3) Activity was present in the T81WS during the previous 4 weeks.
If none of the above situations exists, then the sampling and analysis of this stream need not be performed.
I Sampling and analysis of the dry cooling tower sumps and the auxiliary component cooling water pump discharge will be required only when detectable activity exists in the CCW.
Sampling and analysis of the circulating water discharge-steam generator blowdown heat exchanger discharge (CWD-SGB) will be required only when detectable activity exists in the secondary system.
Table 4.11-1 (Continued)
TABLE NOTATIONS 3
~'
Sampling and analysis of the steam generator blowdown will be required only when the blowdown is directed to the circulating water system or Waterford 3 waste por.d.
Steam generator blowdown to the Waterford 3 waste pond will be limited to situations requiring secondary chemistry control where the Circulating Water System is not available or the secondary chemistry is outside the requirements for Circulating Water System discharge.
Blowdown to the waste pond will be terminated upon detection of sample activity greater than the LLD levels of Table 4.11-1 Section B.
kTo be represe'tative of the quantities and concentration of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream.
I Steam generator blowdown discharge to the waste pond shall be limited to a period of six months with the circulating water system discharge path not available unless radiation monitoring and automatic isolation capabilities are added to the waste pond discharge path.
WATERFORD - UNIT 3 3/4 11-Sa Amendment No. 1
I RADIOACTIVE EFFLUENTS '
(
DOSE LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited:
a.
During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ, and b.
During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.
APPLICABILITI:
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 and submit to the Commission within 30 days, pursuant to Specifica-
'f tion 6.9.2, a Special Report that identifies the cause(s)j or exceeding the limit (s) and defines the corrective actions that
(
have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
This Special Report shall also include (1) the results of radiological analyses of the drinking water source and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR Part 141.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
k WATERFORD - UNIT 3 3/4 11-6
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