ML19347E761
| ML19347E761 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/06/1981 |
| From: | Snyder B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19347E758 | List: |
| References | |
| NUDOCS 8105130333 | |
| Download: ML19347E761 (15) | |
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METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY DOCKET N0. 50-320 THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 15 License No. DPR-73 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Metropolitan Edison Company, Jersey Central Power and Light Company, and Pennsylvania Electric Company (the Licensee) dated February 23, 1981, and supplemented on March 18, 1981, complies with the 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; 8.
The facility will operate in conformity with the Order for Modification of License dated July 20, 1979, the Order of February 11,1980, the Modification of Order dated August 11, 1980, the Amendment of Order dated November 14, 1980, the application for amendment, 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 De 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 regulations and all applicable requirements have been sat's fied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, by chano'ng paragraph 2.C.(2) to facility operating License No. DPR-73, to read as follows:
2.C.(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.15, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and all Commission Orders, issued subsequent to March 28, 1979.
81051303 3 3 g
l 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY C0tttISSION A
,Bernard J. Sny
, Program Director Three Mile Isl nd Program Office Office of Nuclear Reactor Regulation
Attachment:
Revised Technical Specifications r
Date of Issuance: MAY 6 1981 l
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o-FACILITY GPERATING LICENSE NO. DPR-73 DOCKET NO. 50-320 Replace the following pages of Appendix "B" Technical Specifications with the enclosed pages as indicated. The revised pages contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to main-tain document completeness.
- Paops, 2-7 2-8 2-9 2-10d 2-11 2-12 2-13 2-14 2-14b 2-14c 3-21 3-22
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O 2-7 o
LIMITING CONDITIONS FOR OPERATION 2.0 MONITORING REQUIREMENTS 2.1.2 Gaseous Effluents Apol1cability Applies to the controlled release of radioactive gases from TMI Unit Nos. 1 and 2.
Objective Objective e
To define the limits and conditions T0 ensure that radioactive gaseous for the controlled release of radio-releases from the facility are with-active gaseous effluents to the environs in the limits of specifications, to ensure that these releases are as low as practicable. These releases should not result in radiation exposures in offsite areas greater than a few per-cent of background exposures. The instantar.eous release rate for all effluent discharges should be within the limits specified in 10CFR 20.
To assure that the release of radio-active gases to offsite areas meet the as low as practicable concept, the followins objectivas apply:
a.
The release rate of radionuclides, averaged over a yearly interval, ex-cept particula +a nuclides with half lives greater than 8 days, discharged from Unit Nos.1 and 2, should result l
in a dose rate at the site boundary of less than 5 mrem /yr to the whole body or any organ, b.
The release rate of particulate radionuclides with half-lives longer i
than 8 days, should result in a dose I
in the unrestricted area of less v.han 15 mrem /yr by inhalation or to the thyroid of a child through the ccw-milk chain.
Specification Specification 3.
The instantaneous release rate of During release of radioactive gaseous gross gaseous activity except for halo -
wastes, the following conditions gens and particVates with half-lives shall be met:
longer than e',%.'ays shall not ex-ceed:
A.
During release of gaseous waste from the waste gas decay tanks, the 3
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< 1.5 x 105m following conditions shall be met:
7(MPC)j sec Amendment No. 15
2-9 LIMXTING CONDITIONS FOR OPERATION 2.0 MONKTORING REQUIREMENT 5 A
O Specification (Cont'd)
Specification (Cont'd) f.
Radioactive gas and particulates 3.
The valves (Unit 1: AH-VIA and purged from the reactor building shall AH-VIB and Dampers; Unit 2: 05129 be filtered through the high efficiency A/D and 05129 B/C) shall be inter-particulate air filters, locked to close or recirculate, respectively on receipt of a high g.
The maximum activity to be con-radiation signal from the Reactor tained in one gas decay tank shall not Building Exhaust Monitor (Unit 1:
exceed 8800 curies (equivalent to RM-A9; Unit 2: HP-R-225 and HP-R-Xe-133).
226) respectively.
l h.
When the release rate of radio-C.
The flow rate for radioactive active materials in gaseous wastes, effluent streams and the Auxiliary averaged over a calendar quarter and Fuel Handling Building and the
- exceeds, Reactor Building, shall be monitored and recorded. Gaseous effluents 3
3m from the Waste Gas Decay Tanks and Q3 6 x 10 the Reactor Building Purge Exhaust
}(MFC)i sec shall be continuoysly monitored and (noble gas)
- recorded, or D.
Radioactive gaseous waste sampling 0.006 uCi/sec (particulates with and activity analysis shall be per-half-lives greater famed in accordance with Table 2.3-2.
than 8 days)
E.
The waste gas decay tank effluent the licensee shall notify the NRC with-monitor (Unit 1: RM-A7; Unit 2: WDG-R-in 30 days, identifying the causes and 1480) shall be tested using the in-describing the proposed program of ac-stalled check tiurce or equivalent tion to reduce such release rates, prior to any release of radioactive gas from i holdup tank and shall be calibratei quarterly using a re-ferenced calibration source in a controlled reproducible geometry.
F.
During power operation, the con-densor vacuum pump discharge shall be continuously monitored for gross gaseous activity. The monitor shall not be inoperable for more than a week. Whenever this monitor is in-operable, a grab sample shall be taken daily and analyzed for gross radioactivity.
(p,y).
G.
Facility records shall be main-tained of radioactive concentration, release ratio and volume of each batch of gaseous effluents released.
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Amendment No. 15
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2-10d TABLE 2.1-1 (Continued)
TABLE NOTATION b.
Tritium grab samples shall be taken at least once -per 7 days from the ventilation exhaust from the Chemical Cleaning Building.
l c.
The principal gamma emitters for which the LLD specification applies exclusive'y are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-15, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. 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, shal7 also be identified and reported.
Nuclides which are below the LLD for tt.e analyses shall be reported as "less than" the nuclide's LLD and shall not be reported as being present at the LLD level for that nuclide. The "less than" values shall not be used in the required dose calculations, i
1 Amendment No. 15 l
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2-11 TABLE 2.3-2 Radioactive Gaseous Waste Sampling and Analysis (5) 1 Samole Tyoe 5amoling Frecuency Tyce of Activity Anaiysis Detectacle concentration (1)
Waste Gas Decay Tank Release 10~0 uCf/cc Gas Each Tank H-3 Release Individual Gama Emitters 10-4 uC1/cc(2)
Reactor Building Purce Releases Gas Each Purge H-3 10-6 uCi/cc Individual Ganma Emitters 10-4 uCf/cc(2)
Condenser Vacuum Pumo Releases Gas Monthly H-3 10'O uCf/cc Montnly (3)
Individual Gamma Emitters 10-# uCi/cc (2)
Auxiliary and Fuel Handling Building Exhaust Vent, Reactor Building Purge Vent and Unit Exnaust (6)
Vent Release Points Gas Monthly (4)
H-3 10-0 uC1/cc Individual Gama Emitters 10 uCi/cc (2)
Charcoal Weekly (7)
I-131, I-133, I-135 10-12 uCi/cc Particulates Weekly Individual Gama Emitters 10-10 uC1/cc (2)
Monthly Comcosite Sr-89, Sr-90 10-11 uCi/cc Monthly Composite Gross Alpha Emitters 10-11 uCf/cc (1) Une aoove cetectaoility limits are based on technical feasibility and on the potential significance in the environment of the quantities released.
For some nuclides, lower i
detection limits may be readily achievable and when nuclides are measured below the stated limits, they should also be reported, Amendment No. 15
2-13 LIMITING CONDITIONS FOR OPERATION 2.0 MONITORING REQUIRENENTS o
Bases (Cont'd)
Bases (Cont'd)
These efforts should include con-5.6.1 of these Technical Specifica-sideration of meteorological tions. On the basis of such reports conditions during releases, and any additional information the Comission may obtain from the The annual' objectives have been licensee or others, the Comission develope <t taking into account a may from time to time require the 1
combination of system variables licensee to take such action as including fuel failures, primary the Comission deems appropriate.
system leakage, primary to secondary system leakage, and the performance of radionuclide removal mechanisms.
I-131 is not specifically monitored because it has decayed to less than detectable activity since the March 28, 1979, accident.
Specification a above, requires the licensee to limit the con-centration of noble gases from the station to levels specified in 10 CFR 20, Appendix B, for unrestric-ted areas, BasejonaX/Qof 6.7 x 10-0 sec/m*, this specif1-cation provides ascurance that no member of the general public would be exposed to rad %ctive materials in excess of lim'ts specified in the Comission's rules and regulations.
Specification b. above, requires the licensee to limit the concen-tration of particulates with half-lives greater than eight days, l
released from the station to un-restricted areas to levels such that no indi'tidual will receive acre than 500 mren/yr to the tota.1 '/Jdy or 3000 mrem /yr to the skin. The absence of iodine insures that the corres-ponding thyroid dose rate above background to an infant via the cow-milk-infant pathway is less than or equal to 1500 mrem /yr.
i A grazing period of 6 months has been applied to all radionuclides in particulate fann with half-
]
lives greater than eight days, 1
to allow for the milk exposure pathway. The release rate is de-termined by using the methodology of Regulatory Guide I.109 (Rev. 1) of 2.1 x j0 ge dgposition factor (D/Q) and a relati m-The 0/Q of 2.1 x 10- m-2 was. calculated for the nearest cow located 1.2 miles SE of the station, using on-site meteorological data.
Amendment No.15 h
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J 2-14u TABLE 2.1-3a RADI0 ACTIVE GA3EOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION
- 10. EPICOR-II VENTILATION SYSTEM 37 a.
Noble Gas Activity Monitor 1
b.
Deleted
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41
- c..
Particulate Sampler 1
d.
Flow Rate Monitor 1
36 3
d.
Sampler Flow Rate Monitor 1
36 TABLE NOTATION
- At all times.
With the number of channels OPERABLE less than required by the ACTION 36 j
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 />.
ACTION 37 With the number of channels OPERABLE less than required by the Min mum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab d
samples 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 4
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 />.
ACTION 41 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sampling l
equipment as required in Table 2.1-1.
Amendment No.10,15 l
d 2-14c TABLE 2.1-3b RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL SOURCE CHANNEL FUNCTIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST
- 10. EPICOR-II VENTILATION SYSTEM a.
Noble Gas Activity Monitor D
M R(3)
Q(2) b.
Deleted c.
Particulate Sampler W
N.A.
N.A.
N.A.
d.
Flow Rate Monitor D
N.A.
SA SA e.
Sampler Flow Rate Monitor D
N.A.
SA SA TABLE NOTATION (2) CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunication occurs if any of the following conditions exist.
1.
Instrument indicates measured levels above the alarm setpoint.
2.
Circuit failure (alarm function only).
3.
Instrument indicates a downside failure (alarm function only).
4 Instrument controls not set in operate mode or the switch position administratively monitored and controlled.
(3) The initial CHANNEL CALIBRATION shall be 9rformed using one or more of the reference standards certified by t..e National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system 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.
Amendment No. ID,15
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n 3-21 3.1.2.b Terrestrial 3.1.2.b(1) Aerial Remote Sensing Environmental Nnitoring Requirement Deleted.
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Amendment No. 15
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