ML19309B216
| ML19309B216 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/12/1980 |
| From: | Vollmer R NRC - TMI-2 OPERATIONS/SUPPORT TASK FORCE |
| To: | |
| Shared Package | |
| ML19309B207 | List: |
| References | |
| FOIA-80-301 NUDOCS 8004030279 | |
| Download: ML19309B216 (10) | |
Text
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R. C. Arnold MARCH 12, 1980 i
Ms. Susan R. Srley 129 Cocoa Avenue Hershey, Pennsylvania 17033 Mr. David D. Maxwell, Chairman Board of Supervisors Londonderry Township RFD#1, Geyers Church Road Middletown, Pennsylvania 17057 Mr. J. J. Colitz
{
Manager, Plant Engineering Metropolitan Edison Company P.O. Box 480 l
Middletown, Pennsylvania '17057 Governor's Office of State Planning and Development ATTN: COORDINATOR, PENNSYLVANIA CLEARINGHOUSE P.O. Box 1323 i
Harrisburg, Pennsylvania 17120 l
Mr. J. B. Logan, Superintendent, Unit 2 i
Metropolitan Edison Conpany P.O. Box 480 Middletown, Pennsylvania 17057 Mr. G. A. Kunder, Unit 2 Supt.
Technical Support P.O. Box 480 Middletown, Pennsylvania 17057
- Ivan W. Smith, Esq.
Atomic Safety & Licensing Board Panel U.S. Nuclear Regulatory Comission Washington, D.C. 20555
- Atomic Safety and Licensing Appeal Board U.S. Nuclear Regulatory Comission Washington, D.C. 20555
- Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Comission Washington, D.C. 20555
- Docketing and Service Section U.S. Nuclear Regulatory Comission Washington, D.C. 20555 8.004oy(ig g
METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY DOCKET NO. 50-320 THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.10 License No. DPR 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The facility will operate in conformity with the Order for Modifi-cation of License dated October 18, 1979, the provisions of the Atomic Er.ergy Act of 1954, as amended (the Act), and the rules and regulations of the Comission set forth in 10 CFR Chapter I; B.
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 Comission's regulations; C.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and, D.
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.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amend-ment, by changing paragraph 2.C.(2) and by adding paragraphs 2.E.(2),
(3), and (4) to facility operating License No. OPR-73, to read as follows:
2.C.(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.10, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifica-tions and all Commission Orders issued subsequent to March 28, 1979.
2.E.(2) The licensee shall promptly begin the process of decontam-inating the intermediate-level waste water from TMI-2 by operating EPICOR-II. Prior to operation, the licensee shall consult the Director of NRR for approval of the final operating procedures and design and construction details.
In order to reduce the inherent risk from the contaminated water most expeditiously and prudently, the i
licensee should, to the extent pcssible, process all the 1
water once through the EPICOR-II system.
2.E.(3) The licensee shall maintain suitable tankage at TMI-1 that could be used to store waste water from TMI-2 at an appropriate state of readiness, should additional storage become necessary.
2.E.(4) The licensee shall not ship spent resins offsite unless they have been solidified, and only then with the prior approval of the Director of NRR, provided however, that the licensee may ship nonsolidified but 'ewatered spent resins offsite if it determines, and the 'sirector of NRR concurs, that such a shipment is required to assure con-tinued-operation of EPICOR-II or otherwise required to protect public health and safety. The licensee shall expeditiously construct a facility for solidification of the spent resins and shall use such facilities for resin solidification upon receiving the Director of NRR's con-currence with the design and operating procedures.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION n
- f ;y Richard H. Vollmer, Director Three Mile Island Support
Attachment:
Changes to the Technical Specifications Date of Issuance: March 12, 1980
ATTACHMENT TO AMEN 0 MENT N0.10 FACILITY OPERATING LICENSE NO. DPR-73 DOCKET NO. 50-320 Insert pages 2-10a, 2-10b, 2-10c, and 2-10d following page 2-10 in the Appendix B Technical Specifications. These pages include new speciff-cation 2.1.2.J and its associated basec.
Insert new pages 2-14a, 2-14b, 2-14c following page 2-14 in the Appendix B Technical Specifications.
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2-10a GASEOUS EFFLUENTS 2.1.2.J The release rate of radioactive materials, other than noble gases, in gaseous effluents sha'l be determined to be within the limits calculated in accordance with this specification by obtaining representative samples and performing analyses in accordance with the sampling and analysis program, specified in Table 2.1-1.
BASES 2.1.2.J This specification is provided to ensure that the dose at any time at the site boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas.
The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1.
These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not i
, result in the exposure of an individual in an unrestricted area, either within or outside the site boundary, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)). For individuals who may at times be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the site boundary to less than or equal to 500 mrem /yr to the total body or to less than or equal to 3000 mrem /yr to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose L
rate above background to an infant via the cow-milk-infant pathway to less than or equal to 1500 mrem /yr for the nearest cow to the plant.
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Amendment No. 10
TABLE 2.1-1 RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Lower Limit of Gaseous Release Sampling Analysis Type of Activity Detection (LLD)
Type Frequency frequency Analysis (pCi/ml)a lx10-4 b
c EPICOR -II Ventilation M
M Principal Ganna Emitters Grab Sample H-3 lx10~0 rob Pr 1
l g
1 a
8-an O
l-l 2-10c TABLE 2.1-1 (Continued)
TABLE NOTATION a.
The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 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 LLD =
E. V. 2.22. Y. exp l-Aat) i Where.
LLD is the lower limit of detection as defined above (as picocurie i
per unit mass or volume),
sb is the standard deviation of the background coutning rate or of the counting rate of a blank sample as appropriate (as counts per minute),
E is the counting efficiecny (as counts per transfonnation),
V is the sample size (in units of mass or volume),
2.22 is the number of transformations per minute per picocurie, Y is the fractional radiochemical yield (when applicable),
A is the radioactive decay constant for the particular radionuclide, and at is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, nor environmental samples).
The value of sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the back-j ground counting) rate or of the counting rate of the blank samples (as appropriate rather than on an unverified theoretically pre-dicted variance.
In calculating the LLD for a radionuclide deter-mined by gama-ray spectrometry, the background shall inc%de the typical contributions of other radionuclides normally present in the samples. Typical values of E, V, Y, and at shall be used in the calculation. The background count rate is calculated from the background counts that are determined to be with + one FWHM (Full-Width-at-Half-Maximum) energy band about the energy of the gamma ray peak used for the quantitative analysis for that radio-nuclide.
Amendment No. 10
t 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 spent fuel pool area.
c.
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, j
Co-58, Co-60, In-65, 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, shall also be identified and reported. Nuclides which are below the LLD-for the 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.
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Amendment No.10 l
2-14a 2.1.3 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION The radioactive gaseous effluent monitoring instrumentation channels shown in Table 2.1-3a shall be OPERABLE.
APPLICABILITY: As shown in Table 2.1-3a.
ACTION:
With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 2.1-3a.
SURVEILLANCE REQUIREMENTS Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by perfonmance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 2.1-3b (per occupational exposure considerations and detector sensitivity in ambient radiation areas).
BASES 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 of gaseous effluents. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criterion 64 of Appendix A to 10 CFR Part 50.
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Amendment No. 10
2-14b TABLE 2.1-3a RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS i
INSTRUMENT OPERABLE APPLICABILITY ACTION
- 10. EPICOR-II VENTILATION SYSTEM a.
Noble Gas Activity Monitor 1
37 b.
Iodine Sampler 1
41 c.
Particulate Sampler 1
41 d.
Flow Rate Monitor 1
36 e.
Sampler Flow Rate Monitor 1
36 l
l TABLE NOTATION
- At all times.
ACTION 36 - 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 />.
ACTION 37 - 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 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 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
j 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 i
equipment as required in Table 2.i-1.
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Amendment No. 10
2-14c TABLE 2.1-3b RADI0 ACTIVE GASE0US 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..
Iodine Sampler W
N.A.
N.A.
N.A.
c.
Particulate Sampler W
N.A.
N.A.
N.A.
d.
Flow Rate Mon'itor 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 measures levels above the alarm setpoint.
2.
Circuit failure (alann function only).
3.
Instrument indicates a downside failure (alarm function only).
4.
Instrument controls not set in operate mode or the switch position administrative 1y monitored and controlled.
(3) The initial CHANNEL CALIBRATION shall be perfonned 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 participate in measurement assurance activities with NBS. These standards shall pennit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION sources that have been related to the initial calibra-tion shall be used.
l Amendment No. 10 l