ML20212P969
| ML20212P969 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 03/04/1987 |
| From: | Joshua Wilson Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20212P971 | List: |
| References | |
| NUDOCS 8703160432 | |
| Download: ML20212P969 (13) | |
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UNITED STATES
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i NUCLEAR REGULATORY COMMISSION W ASHINGTON, D. C. 20555 g
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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. 17 License No. NPF-38 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The applications for amendment, dated August 20 and October 1, 1986 by Louisiana Power and Light Company (licensee), comply with standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Consnission's regulations set forth in 10 CFR Chapter I; ii B.
The facility will operate in confonnity with the applications, the provisions of the Act, and the regulations of the Comission; 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; i
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
l 2.
Accordinely, 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:
8703160432 870304 PDR ADOCK 05000302 p
a 2-(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 17, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in this license.
LP&L shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION h&
Ja s H. Wilson, Project Manager PWR Project Directorate No. 7 Division of PWR Licensing-B
Attachment:
Changes to the Technical Specifications Date of Issuance: March 4,1987 l
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March 4, 1987
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ATTACHMENT TO LICENSE AMENDMENT NO. 17 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 Paces 3/4 3-55 3/4 3-56 3/4 3-57 3/4 3-58 3/4 3-60 3/4 3-59 3/4 3-63 3/4 3-64 3/4 11-1 3/4 11-2
INSTRUMENTATION RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.30 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm / trip setpoints set tc ensure that the limits of Specification 3.11.1.1 are not exceeded.
The alarm /
trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).
APPLICABILITY:
At all times.
ACTION:
a.
With radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable.
1 b.
With less than the minimum number of radioactive liquid effluent a
monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-12. Restore the inoperable instrumentation to OPERABLE status within 30 days or, if unsuccessful, explain in the next l
Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.8, why this inoperability was not corrected within the time specified.
Releases need not be terminated after 30 days provided the specified ACTIONS are continued.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.10 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-8.
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i WATERFORD - UNIT 3 3/4 3-55 AMENDMENT NO.17 f
g TABLE 3.3-12 Og RADI0 ACTIVE LIQUID FFFLUENT MONITORING INSTRIMENTATION og MINIMUM CHANNEL 5 INSTRtMENT OPERABLE ACTION e
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1.
RADI0 ACTIVITY MONITORS PROVIDING ALAPM AND AUTOMATIC TERMINATION OF RELEASE w
a.
Boric Acid Condensate Discharge 1
28 b.
Waste, Waste Condensate and Laundry Discharge 1
28 c.
u.; Cooling Tower Sumps 1/ sump 29 d.
Turbine Building Industrial Waste Sump 1
29 u
\\
1 Circulating Water Discharge (Blowdown Heat Exchanger e.
and Auxiliary Component Cooling Water Pumps)#
1 29 2.
CONTINUOUS COMPOSITE SAMPLERS a.
Steam Generator Blowdown Effluent Line 1
29 3.
FLOW RATE MEASUREMENT DEVICES a.
Boric Acid Condensate Discharge 1
30 b.
Waste, Waste Condensate and Laundry Discharge 1
30 c.
Turbine Building Industrial Waste Sump
- N.A.
N.A.
5 S
d.
Dry Cooling Tower Sumps
- N.A.
N.A.
R e.
Circulating Water Discharge * (Blowdown and Blowdown Heat l
Exchanger and Auxiliary Component Cooling Water Pumps)
N.A.
N.A.
- Automatic termination of blowdown discharge only f
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TABLE 3.3-12 (Continued)
TABLE NOTATIONS
- Pump performance curves generated in place shalf 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 provided best efforts are made to repair the instrument and 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; l
ACTION 29 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided best efforts are made to repair the instrument and that grab samples are analyzed for radioactivity at a lower limit of detection of at least 10-7 microcurie /mL.
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 / gram of a.
the secondary coolant is greater than 0.01 microcurie DOSE EQUIVALENT I-131, or 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 provided best efforts are made to repair the instrument and that 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 AMENDMENT NO.17 1
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TABLE 4.3-8 E
RADIDACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 42 CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST E
O 1.
RADI0 ACTIVITY MONITORS PROVIDING ALARMS AND AUTOMATIC TERMINATION w
OF RELEASE Boric Acid Condensate Discharge P
P R(3)
Q(1) a.
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)
Circulating Water Discharge e.
(Blowdown Heat Exchanger and w1 Auxiligry Component Cooling Water Pumps)
D M
R(3)
Q(5) w*
2.
CONTINUOUS COMPOSITE SAMPLERS a.
Steam Generator Blowdown Ef fluent Line D(6)
N.A.
R Q
3.
FLOW RATE MEASUREMENT DEVICES Boric Acid Condensate Discharge D(4)
N.A.
R Q
a.
b.
Waste, Waste Condensate and Laundry D(4)
N.A.
R Q
Discharge g
Turbine Building Industrial Waste Sump N.A.
N.A.
N.A.
N'. A.
c.
g d.
Dry Cooling Tower Sumps N.A.
M.A.
N.A.
N.A.
k Circulating Water Discharge e.
2, (Blowdown and Blowdow+. Heat l
Exchangers and Auxiliary 2
?
Component Cooling Water Pumps)
~ N.A.
N.A.
N.A.
N.A.
8 Automatic termination of Blowdown discharge only
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TABLE 4.3-8 (Continued)
TABLE NOTATION (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation l
of this path ay 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, i
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 j
1.
Instrument indicates measured levels above the alarm setpoint.
2.
Circuit failure.
-f (3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards er using standards that have been obtained from suppliers that participate i
1 in measurement assurance activities with NBS. These standards shall 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 i
of this pathway occurs if the instrument indicates measured levels above i
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.
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Circuit failure.
I 3.
Instrument controls not set in operate mode.
l (6) CHANNEL CHECA 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
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continuous releases are made to the Circulating Water System or Waterford 3 waste pond.
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WATERFORD - UNIT 3 3/4 3 59 Amendment No. 1 i
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INSTRUMENTATION RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION i
3.3.3.11 The radioactive gaseous effluent monitoring instrumentation 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 alarm /
trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.
APPLICABILITY:
As shown in Table 3.3-13.
ACTION:
a.
With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably l
conservative.
b.
With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-13.
Restore the inoperable instrumentation to OPERABLE status within 30 days or, if unsuccessful, explain in the next Semi-l annual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.8, why this inoperability was not corrected within the time specified.
Releases need not be terminated after 30 days provided i
the specified ACTIONS are continued.
I 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 I
shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-9.
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WATERFORD UNIT 3 3/4 3-60 AMENDMENT NO.17 t
TABLE 3.3-13 (Continued)
TABLE NOTATIONS
- At all times.
- 0uring WASTE GAS HOLDUP SYSTEM operation.
- With irradiated fuel in the storage pool.
ACTION STATEMENTS 4CTION 35 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment provided best offorts are made to repair the instrument and that prior to initiating the release:
a.
At least two independent samples of the tank's cor. tents are analyzed, and b.
At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup; ACTION 36 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided best efforts are made to re-pair the instrument and that 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 />.
For the waste gas holdup tank this action item is applicable only during periods of release.
For the main condenser evacuation and turbine gland sealing systems, this action item applies only during release via the discharge silencer and only during turbine gland sealing operations and/or vacuum pump operation.
ACTION 37 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, offluent releases via this pathway may continue provided best efforts are made to re-pair the instrument and that grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
However, containment purging of radioactive effluents must be immediately suspended during this condition for the plant stack only.
ACTION 38 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of the WASTE GAS HOLDUP SYSTEM may continue provided >est efforts are made to repair the instrument and that grab samples are collected 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 analyzed within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for the onservice gas decay tank.
WATERFORD - UNIT 3 3/4 3 63 AMEN 0 MENT NO.17
TABLE 3.3-13 (Continued)
ACTION STATEMENTS ACTION 39 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided best efforts are made to repair the instrument and that samples are continuously collected with auxiliary sampling equipment as required in Table 4.11-2.
ACTION 40 -
With the number of channels OPERABLE one less than required by the Minimum Chanrels OPERABLE requirement, operation of the WASTE GAS HOLOUP SYSTEM may continue provided best efforts l
are made to repair the instrument and that the system is sampled by either the remaining monitor or by a grab sample at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and the oxygen concentration remains less than i
2%.
If there are no monitors OPERABLE, WASTE GAS HOLDUP SYSTEM operation may continue provided best efforts are made to return at least one channel to OPERABLE status and that a grab sample is taken and analyzed from the onservice gas decay tank at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and the oxygen concentration r.anains less than 1%. With oxygen concentration exceeding 1%, reduce the oxygen concentration to less than 1% within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, or be in HOT.
STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
e WATERFORD UNIT 3 3/4 3-64 AMEN 0 MENT NO. I 7
3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS P
CONCENTRATION LIMITING CONDITION FOR OPERATION i
3.11.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.
For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10 4 microcurie /ml total activity.
APPLICABILITY:
At all times, j
ACTION:
With the concentration of radioactive material released in liquid effluents J
to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits, and describe the events leading to
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this condition in the next Semiannual Radioactive Effluent Release Report.
l SURVEILLANCE REQUIREMENTS 4
4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11-1.
4.11.1.1.2 The results of the radioactivity analyses shall be used in accor-dance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of Specification 3.11.1.1.
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WATERFORD UNIT 3 3/4 11-1 AMENDMENT NO. 17 l
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TABLE 4.11-1 RADI0 ACTIVE LIQUl0 WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMll MINIMUM OF DETECTION LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLO)a TYPE FREQUENCY FREQUENCY ANALYSIS (pCi/mL)
A. Batch Waste P
P Release Each Batch Each Batch Principal Gamma 5x10 7 Tanks 'I'9'h'I Emitters D
C
- 1. Boric Acid 1-131 1x10 0 Condensate P
M Dissolved and 1x10 6 Entrained Gases
- 2. Waste One Batch /M (Gamma Emitters)
Condensate P
M H-3 1x10 5 d
Each Batch Composite
- 3. Laundry Gross Alpha 1x10 7 Waste
(
- 4. Turbine P
Q Sr-89, Sr-90
$>10 6 d
Building Each Batch Composite Industrial Waste Fe-55 1x10 0 Sumps *
- 5. Ory Cooling Tower Sumps
- 1 and #2*
- 6. Regenerative Waste
- 7. Filter Flush B. Waste
'unan release from this source is batch in nature.
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WATERFORD - UNIT 3 3/4 11-2
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