ML20214K529
| ML20214K529 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 08/13/1986 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20214K519 | List: |
| References | |
| NUDOCS 8608210189 | |
| Download: ML20214K529 (16) | |
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UNITED STATES 4y g
NUCLEAR REGULATORY COMMISSION s
c
-l WASHINGTON, D. C. 20555
,o COMMONWEALTH EDISON COMPANY DOCKET NO. 50-237 D_RESDEN NUCLEAR POWER STATION, UNIT NO. 2 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 93 License No. DPR-19 1.
The Puclear Reculatory Commission (the Comission) has found that:
A.
The aoplication for amendment by the Comonwealth Edison Company (the licensee) dated December 4, 1984, complies with the standards and requirements of the Atomic Eneroy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's reculations and all applicable requirements have been satisfied.
P i
. 1 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paraaraoh 3.R. of Provisional Operatina License No. DPR-19 is hereby amended to read as follows:
R.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 93, are hereby incorporated in the license. The licensee shall operate the facility in acenrdance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FORTHENUCLEAD.REr,ULATORYt0MMTSSION John
. Zwolinski, Director BWR P o.iect Directorate #1 Division of RWR Licensing
Attachment:
Chances to the Technical Specifications n te o# issuance: August 13, 1986 a
f
- g=r: ~ :.
.+-
ATTACHMENT:TO LICENSE AMENCNENT NO. 93 PROVISIONAL OPERATING LICENSE DPR-19 l00dKETNO.50-237 3
Revise Appendix A Technical Specifications by removino the paces identified below and inserting the attached pages. The revised pages are identified by the captionad amendment number and contain marginal lines indicating the area of charge.
REMOVE INSERT 3/4.?-15 3/4.?-15 3/4.2-24 3/4.2-24 3/4.7.-? 5 3/4.?-25 3/4.8-22 3/4.8-27 3/4.8-?3 3/4.8-23 I
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DRESDEN II DPR-19 Amendment C2. $d! p6 $ $
TABLE 3.2.5 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimuu of Oper Total Nc.
Channe' jl of Chant.el?
Parameter Action (2) 1 2
SJAE Radiation Activity Monitor D
1 3
Main Chimney Noble Gas SPING/CE A
Low Range Activity Monitor 1
1 Main Chimney SPING Noble Gas
- A Monitors Mid, Hi Range 1
1 Main Chimney Iodine Sampler C
1 1
Main Chimney Particulate Sampler C
1 1
Main Chimney Flow Rate Monitor B
1 1
Main Chimney Sampler Flow B
Rate Monitor 1
2 Reactor Building Vent Exhaust E
Duct Radiation Monitor 1
1 Reactor Building Vent SPING Noble F
Gas Monitor Low, Mid, High Range 1
1 Reactor Building Vent Flow Rate B
Monitor 1
1 Reactor Building Vent Sampler Flow B
Rate Monitor 1
1 Reactor Building Vent I'odine C
Sampler 1
1 Reactor Building Vent Particulate C
Sampler 1
1 MVRS Process Exhaust Iodine Sampler E
1 1
MVRS Process Exhaust Particulate Sampler E
1 1
MVRS NVAC Exhaust Iodine Sampler E
1 1
MVRS HVAC Exhaust Particulate Sampler E-Notes:
(See Next Page) 3/4.2-15 3960a 3843A
DRESDEN II DPR-19 Pf, $, ' 96 S0 d
Amendment N).
s TABLE 4.2.3 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Instrument Calibration Function Test Source Instrument check (1)(6)
(1)(6)(3)
(1)(4)(2)(6)
Check (1)
SJAE Radiation D
R Q
R Activity Monitor Reactor Blds Vent D (4)
N/A N/A N/A Particulate and Iodine Sampler Reactor Bldg Vent D
R Q
Q Exhaust Duct Radiation Monitor Reactor Blds Vent D
R Q
M SPING Noble Gas Monitor Lo, Mid, High Range Main Chimney Noble D
R Q
M Gas Activity Monitor Main Chimney SPING D
R Q
M Noble Gas Monitor Lo, Mid High Range Main Chimney D (4)
N/A N/A N/A Particulate and Iodine Sampler Main Chimney Flow D
R Q
N/A Rate Monitor Main Chimney Sampler D
R Q (5)
N/A Flow Rate Monitor Reactor Blds Vent D
R Q
N/A Flow Rate Monitor Reactor Bldg Sampler D
R Q (5)
N/A Flow Rate Monitor MVRS Process Exhaust D (7)
N/A N/A N/A Iodine and Particulate Sampler MVRS HVAC Exhaust Iodine D (7)
N/A N/A N/A and Particulate Sampler Notes:
(See Next Page) 3/4.2-24 3960a 3843A
DRESDEN II DPR-19 Amendment N3. p@, 96, $6 9 $
TABLE 4.2.3 (Notes) 1.
D = Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> M = Once per 31 days Q = Once per 92 days R = Once per refueling cutage 2.
The Instrument Functional Test shall also demonstrate that control room alarm annunciation occurs, if any of the following conditions exist, where applicable.
a.
Instrument indicates levels above the alarm setpoint.
b.
Circuit Failure.
c.
Instrument indicates a downscale failure.
d.
Instrument controls not set in OPERATE mode.
3.
Calibration shall include performance of a functional test.
4.
Instrument check to verify operability of sampler; that the sampler is in place and functioning properly.
5.
Function Test shall be performed on local switches providing low flow alarm.
6.
Function test calibrations and instrument checks are not required when these instruments are not required to be operable or are tripped.
Calibration shall be performed once per refueling outage and not more than once every 18 months. Instrument checks shall be performed at least once per day during those periods when the instruments are required to be operabic.
7.
Instrument check to verify operability of sampler; that the sampler is in place and functioning properly prior to use of the Mobile Volume Reduction System (MVRS).
3/4.2-25 3960a 3843A
DRESDEN II DPR-19 Amendment N2. %,2[ $ $
Table 4.8.1 RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MININUM LOWER LIMIT OF GASEOUS SAMPLING ANALYSIS TYPE OF DETECTION (LLD)
RELEASE TYPE FREQUENCY (7)
FREQUENCY (7)
ACTIVITY ANALYSIS (uCl/ml)
(1) l Principal A. Main Chimney M
M(2)
Gamma Emmitters(5) 1 X 10-4 Reactor Bldg.
Tritium 1 X 10-6 Vent Stack B. All Release Continuous (4)
WI3)
I-131 1 X 10-12 Types as Iodine I-133 1 X 10-10 l
Listed in Sample A above Principal Continuous (4)
W(3)
Gamma Emitters (5) 1 x 10-11 Particulate (I-131, others)
Sample Continuous (4)
Q Sr-89 1
.6 1-11 Composite Particulate Sr-90 1 X 10-11 Sample Continuous (4)
Q Gross f.1pha 1 X 10-11 Composite Particulate Sample C. Main Chimney Continuous (4)
Noble 1 X 10-6 Gas Monitor Noble Cases D. Reactor Bldg.
Continuous (4)
Noble Noble Cases 1 X 10-4 Vent Stack Gas Monitor E. NVR5 Process Continuous (4)
W(6)
I-131 1 X 10-12 Exhaust Sampler Iodine I-133 1 X 10-10 Sample Continuous (A)
W(6)
Principal 1 X 10-11 Particulate Gamma Emitters (S)
Sample (I-131. others)
F. MVRS KVAC Continuous (4)
W(6)
I-131 1 X 10-12 Exhaust Sampler Iodine I-133 1 X 10-10 Sample Continuous (4)
W(6)
Principal 1 X 10-11 Particulate Gamma Emitters (5)
Sample (I-131. others) 3/4.8-22 3817a 3843A
DRESDEN II DPR-19 AmendmentNs.fd..p6 $$
t. '
TABLE 4.8.1 (Continued)
TABLE NOTATION 1.
The lower limit of detection (LLD) is defined in notation A of Table 4.8.6.
7 2.
Sampling and analyses shall also be performed following shutdown,
.startup, or a thermal power change exceeding 20 percent of rated thermal 4
power in I hour unless (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of 5, and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3.
3.
Samples shall be changed at least once per 7 days and the analyses l
completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after removal from the sampler. Sampling shall also be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following each shutdown, startup, or.
i thermal power level change exceeding 20% of rated thermal power in one hour. 'This requirement does not apply if 1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of 5, and 2) the noble gas activity monitor shows that i
effluent activity has not increased by more than a factor of 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.
4.
The ratio of sample flow rate to the sampled strean flow rate shall be knowa.
5.
The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides:
Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions, and Mn-54, Fe-59, l
Co-60, 2n-65, Co-58, Mo-99, Ct-134, Cs-137 Ce-141, and Ce-144 for particulate emissions. Other peaks which are measurable and identifiable by gamma ray spectrometry, together with the above nuclides, shall be also identified and reported when an actual analysis is performed on a sample. Nuclides which are below the LLD for the analyser shall not be reported as being Present at the LLD level for that nuclide.
i 6.
Sampler shall be changed at least once per 7 days or whenever the Mobile Volume Reduction System (NVRS) is shutdown for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and the analyses completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after removal from the sampler.
7.
W = once per week i
M = once per 31 days Q = once per 92 days l
3/4.8-23 l
3817a 3843A l
.m..
UNITED STATES V
h NUCLEAR REGULATORY COMMISSION h
,, j WASHINGTON. D. C. 20655 a
t COMMONWEALTH EDISON COMPANY DOCKET N0. 50-249 4
DRESDEN NUCLEAR POWER STATION, UNIT NO. 3 AMENDMENT TO' FACILITY OPERATING LICENSE i
Amendment No. 88 License No. DPR-25 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for arendment by the Comonwealth Edison Company (the licensee) dated December 4, 1984, complies with the, standards and reauirements of the Atomic Eneray Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act and the rules and regulations of the Commission; C.
There is reasonable' assurance (i) that the activities authorized by this amendment can be conducted without endannerino 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 common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable reouirements have been satisfied.
l
August 13,1986 i
. 2.
Accordingly, the license is amended by channes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.B. of Facility Operatina License No. DPR-25 is hereby amended to read as follows:
R.
Technical Soecifications The Technical Specifications contained in Appendix A, as revised throuch Amendment No. 88, are bereby incorporated in the license. The licensee shall onerate the facilitv in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGUTAT0iY COMMISSION John Zwolinski, nirector RWR ro.iect Directorate di Division of BWR Licensino
Attachment:
Changes to the Technical Specifications-Date of Issuance: August 13, 1986 i
ATTACHMENT TO LICENSE AMENDMENT NO. 88 FACILITY OPERATING LICENSE DPR-25 DOCKET NO. 50-249 Revise Appendix A Technical Specifications by removina the pages identified below and insertino the attached pages. The revised pages are identified by the caotioned amendment number and contain marginal lines indicating the area of chance.
REMOVE INSERT 3/4.2-15 3/4.?-15 3/4.2-24 3/4.2-24 3/4.2-25 3/4.2-25 3/4.8-22 3/4.8-2P 3/4.8-23 3/4.8-23 W
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DRESDEN III DPR-25 Amendment No. }d.) )d $$
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Minimum No.
of Operable Total No.
Channels (1) of Channels Parameter Action (2) 1 2
SJAE Radiation Activity Monitor D
1 3
Main Chimney Noble Gas SPING/CE A
Low Range Activity Monitor 1
1 Main Chimney SPING Noble Gas A
Monitors Mid, Hi Range 1
1 Main Chimney Iodine Sampler C
1 1
Main Chimney Particulate Sampler C
1 1
Main Chimney Flow Rate Monitor B
1 1
Main Chimney Sampler Flow B
Rate Monitor 1
2 Reactor Building Vent Exhaust E
Duct Radiation Monitor 1
1 Reactor Building Vent SPING Noble ~
F Cas Monitor Low, Mid, High Range 1
1 Reactor Building Vent Flow Rate B
Monitor 1
1 Reactor Building Vent Sampler Flow B
Rate Monitor 1
1 Reactor Building Vent Iodine C
Sampler 1
1 Reactor Building Vent Particulate C
Sampler 1
1 MVRS Process Exhaust Iodine E
Sampler 1
1 MVRS Process Exhaust Particulate E
Sampler 1
Sampler 2
1 MVRS KVAC Exhaust Particulate E
Sampler
~
Notes:
(See Next Page) 3/4.2-15 3840a 3845A
DREsogy 777 DPR-25 mendment Wo, g A P$ss TABLg 4.2.3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Instrument Calibration Function Test Source Instrument check (1)(6)
(1)(6)(3)
(1)(4)(2)(6)
Check (1)
SJAE Radiation D
R Q
R Activity Monitor Reactor Bldg Vent D (4)
N/A N/A N/A Particulate and Iodine Sampler Reactor Blds Vent D
R Q
Q Exhaust Duct Radiation Monitor Reactor Bldg Vent D
R Q
M SPINC Noble Gas Monitor Lo, Mid, High P.ange Main Chimney Noble D
R Q
M Gas Activity Monitor Main Chimney SPING D
R Q
M Noble Gas Monitor Lo, Mid, High Range Main Chimney D (4)
N/A N/A N/A Particulate and Iodine Sampler Main Chimney Flow D
R Q
N/A Rate Monitor Main Chimney Sampler D
R Q (5)
N/A Flow Rate Monitor Reactor Blds Vent D
R Q
N/A Flow Rate Monitor Reactor Blds Sampler D
R Q (5)
N/A Flow Rata Monitor MVRS Process Exhaust D(7)
N/A N/A N/A Iodine and Particulate Sampler MVRS HVAC Exhaust Iodine D(7)
N/A N/A N/A and Particulate Sampler Notes:
(See Next Page) 3/4.2-24 3840a 3845A
DRESDEN III DPR-25 d
Amendment No. }6 pf, $,2 4
TABLE 4.2.3 (Notes')
7-1.
D = Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
-M = Once per 31 days Q = Once per 92 days R = Once per refueling outage 2.
The Instrument Functional Test shall also demonstrate that control room alaen annunciation occurs, if any of the following conditions exist, where applic'ble.
a Instrument indicates levels above the alarm setpoint, a.
b.
Circuit Failure.
c.
Instrument indicates a downscale failure.
d.
Instrument controls not set in OPERATE mode.
3.
Calibration shall include performance of a functional test.
4.
Instrument check to verify operability of sampler; that the sampler is in place and functioning properly.
5.
Function Test shall be performed on local switches providing low flow alarm.
6.
Function test calibrations and instrument checks are not required when these instruments are not required to be operable or are tripped.
Calibration shall be performed once per refueling outage and not more than once every 18 months. Instrument checks shall be performed at least once i
per day during those periods when the instruments are required to be operable.
1 7.
Instrument check to verify' operability of sampler; that the sampler is in place and functioning properly prior to use of the Mobile Volume Reduction System (MVRS).
l l
3/4.2-25 l
l l
l
. 3840a i
3845A l
DRESDEN III DPR-25 Amendment No J,hPf I I d
RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MININUM LOWER LIMIT OF GASEOUS SAMPLING ANALYSIS TYPE OF DETECTION (LLD)
RELEASE TYPE FREQUENCY (7)
FREQUENCY (7)
ACTIVITY ANALYSIS (uCl/ml)
(1)I Principal A. Main Chimney M
MI2)
Gamma Emmitters(S) 1 X 10-4 Reactor Bldg.
Tritium 1 X 10-6 Vent Stack B. All Release Continuous (4)
W(3) 1-131 1 X 10-12 Types as Iodine I-133 1 X 10-10 l
Listed in Sample A above Principal Continuous (4)
WI3)
Gamma Emitters (S) 1 X 10-11 Particulate (I-131, others)
Sample Continuous (4)
Q Sr-89 1 X 10-11 Composite Particulate Sr-90 1 X 10-11 Sample Continuous (4)
Q Cross Alpha 1 X 10-11 Composite Particulate Sample C. Main Chimney Continuous (4)
Noble 1 X 10-6 Gas Monitor Noble Cases D. Reactor Bids.
Continuous (4)
Noble Noble Gases 1 X 10-4 Vent Stack Gas Monitor E. MVRS Process Continuous (4)
W(6)
I-131 1 X 10-12 Exhaust Iodine I-133 1 X 10-10 Sampler Sample Principal Continuous (4)
W(0)
Gamme Emitters (5) 1 y 10-11 Particulate (I-131, others)
Sample F. MVRS HVAC Continuous (4)
W(6)
I-131 1 X 10-12 Exhaust Iodine I-133 1 X 10-10 Sampler Sample Principal Continuous (4)
W(6)
Gamma Emitters (5) 1 X 10-11 Particulate (I-131, others) i Sample 1
3/4.8-22 3844a 0009A
tu DRESDEN III DPR-25 Ame dment N2. pf, )dg 8 TABLE 4.8.1 (Continued)
TABLE NOTATION i
1.
The lower limit of detection (LLD) is defined in notation A of Table 4.8.6.
2.
Sampling and analyses shall also be performed following shutdown, startup, or a thermal power change exceeding 20 percent of rated thermal power in I hour unless (1) analysis shows that the DOSE EQU1 VALENT I-131 concentration in the primary coolant has not increased more than a factor of 5, and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3.
3.
Samples shall be changed at least once per 7 days and the analyses completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after removal from the sampler.
Sampling shall also be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following each shutdown, startup, or thermal power level change exceeding 20% of rated thermal power in'one hour. This requirement does not apply if 1) analysis shows that the DOSE EQU1 VALENT I-131 concentration in the primary coolant has not increased more than a factor of 5, and 2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 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.
4.
The ratio of sample flow rate to the sampled stream flow rate shall be known.
I 5.
The principal samma emitters for which the LLD specification applies exclusively are the following radionuclides:
Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions, and Mn-54 Fe-59, Co-60, 2n-65, co-58, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions. Other peaks which are measurable and identifiable by gamma ray spectrometry, together with the above nuclides, shall be also identified and reported when an actual analysis is performed on a sample. Nuclides which are below the LLD for the analyses shall not be reported as being present at the LLD level for that nuclide.
i 6.
Samples shall be changed at least once per 7 days oriwhenever the Mobile Volume Reduction System (MVRS) is shutdown for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and the analyses completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after removal from the sampler.
7.
W = once per week i
M = once per 31 days Q = once per 92 days 3/4.8-23 3844a 0009A m-- -
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