ML20245E101
| ML20245E101 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 06/19/1989 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20245E104 | List: |
| References | |
| NUDOCS 8906270326 | |
| Download: ML20245E101 (14) | |
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jo UNITED STATES g
NUCLEAR REGULATORY COMMISSION o
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PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-352 LIMERICK GENERATING STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 26 License No. NPF-39 1.
The Nuclear Regulatory Commission (the Commission) has found that A.
The application for amendment by Philadelphia Electric Company (the licensee) dated January 27, 1989, 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; 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 (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 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 satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to tiiis licesite sinendment, ana paragraph 2.C.~(2) of Facility Operating License No. NPF-39 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A and the 1
Environmental Protection Plan contained in Appendix B, as revised
.)
through Amendment No.
26, are hereby incorporated into this i
license. Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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This license amendment is effective upon issuance of an operating license-to Limerick Generating Station, Unit-No. 2.
FOR THE NUCLEAR REGULATORY COMMISSION
-/s/
Walter R. Butler, Direc' tor Project Directorate'I-2 Division of Reactor Projects I/II
Attachment:
Changes to.the Technical Specifications Datu of Issuance: June 19, 1989 PD PDI-2/P 0
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This license amendment is effective upon issuance of an operating license to Limerick Generating Station, Unit No. 2.
FOR THE NUCLEAR REGULATORY COMMISSION i
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U Walter R. Gutler, Director Project Directorate I-2 Division of Reactor Projects I/II i
Attachment:
j Changes to the Technical Specifications 1
Date of Issuance: June 19, 1989 n.
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ATTACHMENT TO LICENSE AMENDMENT N0. 26 FACILITY OPERATING LICENSE N0. NPF-39 DOCKET NO. 50-352 Replace the'following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and-contain vertical lines indicating the area of-change. Overleaf pages are provided to maintain document completeness.*
Remove
- Insert 3/4 11-5
. 3/4 11-5 l
3/4 11-6 3/4 11-6 3/4 11-11 3/4.11-11*
3/4 11-12 3/4 11-12 3/4 11-13 3/4 11-13 3/4 11-14
' 3/4 11-14 B 3/4 11-1 B 3/4 11-1 8 3/4 11-2 B 3/4 11-2 6-17 6-17 6-18 6-18*
O 4
_____________m___.__m_
____m-m__. _ _. _ _. _ _ _.
___--___m-______m.._
.-_m_____-_m____.
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 from the site to UNRESTRICTED AREAS (See l Figure 5.1.3-1) shall be limited:
a.
During any calendar quarter to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ, and b.
During any calendar year to less than or equal to 6 mrems to the total body and to less than or equal to 20 mrems to any organ.
1 APPLICABILITY:
At all times.
ACTION:
a.
With the calculated dose from the release of radioactive materials
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in liquid effluents exceeding any of the above limits, prepare and I
submit to the Commission within 30 days, pursuant to Specifica-j tion 6.9.2, a Special Report which identifies the cause(s) for 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 the radiological impact on finished drinking water supplies at the
- nearest downstream drinking water source.
b.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS i
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.
LIMERICK - UNIT 1 3/4 11-5 Amendment No. 26 I
RADI0 ACTIVE EFFLUENTS
_ LIQUID RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.1.3 The liquid radwaste treetment system shall be OPERABLE and appropri-ate portions of the system shall be used to reduce the radioactive materials in liquid waste prior to their discharge when the projected doses due to the liquid effluent, from the site to UNRESTRICTED AREAS (see Figure 5.1.3-1) would exceed l
0.06 mrem to the total body or 0.2 mrem to any organ in a 31-day period.
APPLICABILITY:
At all times.
ACTION:
With radioactive liquid waste being discharged without treatment and a.
in excess of the above limits, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report which includes the following information:
1.
Explanation of what liquid radwaste was being discharged without treatment, identification of any inoperable equipment or sub-systems, and the reason for the inoperability, 2.
Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.
Summary description of action (s) taken to prevent a recurrence.
b.
~ The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases from the site to UNRESTRICTED l
AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM.
4.11.1.3.2 The liquid radwaste treatment system shall be demonstrated OPERABLE by meeting Specifications 3.11.1.1 and 3.11.1.2.
1 LIMERICK - UNIT 1 3/4 11-6 Amendment No. 26
TABLE 4.11.2.1.2-1 (Continued)
TABLE NOTATIONS b
Sampling and analyses shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of the RATED THERMAL POWER within a 1-hour period.
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 3; and (2) the main condenser offgas pre-treatment radioactivity monitor shows that effluent activity has not increased more than a factor of 3.
Samples shall be changed at least once per 7 days and analyses shall be c
completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from sampler.
Sampling shall also be performed at least once per.24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown, startup, or THERMAL POWER change exceeding 15% of RATED THERMAL POWER in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and analyses completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. 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 LLDs may be increased by a factor of 10.
This requirement l
does not apply if (1) analysis shows that the DOSE EQUIVALENT I-131 I
concentration in the primary coolant has not increased more than a.
factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.
d The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.11.2.1, 3.11.2.2, and 3.11.2.3.
The principal gamma emitters for which the LLD specification applies e
include the following radionuclides:
Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, Xe-135m and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-131, Cs-134, Cs-137, Ce-141 and Ce-144 for par-ticulate emissions.
This list does not mean that only these nuclides are to be considered.
Other gamma peaks which are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report, pursuant to Specifica-tion 6.9.1.8.
f Under the provisions of footnote e. above, only noble gases need to be considered.
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g Required only when handling or storing frradiated fuel in the secondary containment.
h.
Required for the hot maintenance shop ventilation exhaust only during opera-tion of the hot maintenance shop ventilation exhaust system.
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LIMERICK - UNIT 1 3/4 11-11
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l RADI0 ACTIVE EFFLUENTS
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DOSE - NOBLE GASES I
LIMITING CONDITION FOR OPERATION 1
3.11.<. 2 The air dose due to noble gases released in gaseous effluents, from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1.3-1) shall l
be limited to the following:
a.
During any calendar quarter:
Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation, and b.
During any calendar year:
Less than or equal to 20 mrads for gamma radiation and less than or equal to 40 mrads for beta radiation.
APPLICABILITY:
At all times.
ACTION:
With the calculated air dose from radioactive noble gases in gaseous a.
effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for 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.
b.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.2 Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
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LIMERICK - UNIT 1 3/4 11-12 Amendment No. 26 i
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RADI0 ACTIVE EFFLUENTS DOSE - IODINE-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, and all radionuclides in particulate fon. with half-lives greater than8daysingaseouseffluentsreleased,fromthesitetoareasatandbeyondl the SITE BOUNDARY (see Figure 5.1.3-1) shall be limited to the following:
a.
During any calendar quarter:
Less than or equal to 15 mrems to any l
organ and, b.
During any calendar year:
Less than or equal to 30 mrems to any l
organ.
APPLICABILITY:
At all times.
ACTIO_N:
With the calculated dose from the release of iodina-131, iodine-133, a.
tritium, and radionuclides in particulate form witn half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant
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to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit-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.
b.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.3 Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
LIMERICK - UNIT 1 3/4 11-13 Amendment No. 26 l
'. 4 RADI0 ACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT ' SYSTEM LIMITING CONDITION FOR OPERATION 3.11.2.4 The VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE and appropriate portions of the system shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1.3-1) when averaged over 31 days would exceed 0.6 mrem to any organ in a 31-day period.
APPLICABILITY:
At all times.
ACTION:
With gaseous waste being discharged without treatment, and in excess a.
of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information:
1.
Explanation of why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability, 2.
Action (s) taken to' restore the inoperable equipment to OPERABLE status, and
- 3.
Summary description of action (s) taken to prevent a recurrence.
b.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases from the site to areas at and beyond l
the SITE boundary shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM.
4.11.2.4.2 The VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by meeting Specifications 3.11.2.1, 3.11.2.2, and 3.11.2.3.
LIMERICK - UNIT 1 3/4 11-14 Amendment No. 26
3/4.11 RADI0 ACTIVE EFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 CONCENTRATION This specification is provided to ensure that the concentration of radio-active materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II, Column 2.
This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR 20.106(e) to the population. 'The concentration limits for dissolved or entrained noble gases are based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air was converted to an equivalent' concentration in water using the methods described in the International Commission on Radiological Protection (ICRP) Publication 2.
The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs).
Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L. A., " Limits for Qualitative Detec-tion and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K., " Detection Limits. for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
3/4.11.1.2 DOSE This specification is provided to haplement the requirements of Sections II. A,
.III. A, and IV. A of Appendix I,10 CFR Part 50.
The Limiting Condition for Opera-tion implements the guides set forth in Section II. A of Appendix I.
The ACTION statements provide the required operating flexibility and at the same time imple-ment the guides set forth in Section IV.A of Appendix I'to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclides concentrations in the finished drinking water that are in excess of the requirements of 40 CFR Part 141.
The dose calculation methodology and parameters in the ODCM implement the require-ments in Section III.A of Appendix I that conformance with the guides of Appendix I be show'n by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.
The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid efflu-ents are consistent with the methodology provided in Regulatory Guide 1.109,
" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.
This specification applies to the release of radioactive materials in liquid effluents from the site.
LIMERICK - UNIT 1 B 3/4 11-1 Amendment No. 26
RADI0 ACTIVE EFFLUENTS BASES 3/4.11.1.3 LIQUID RADWASTE TREATMENT SYSTEM The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable".
This specification implements the requirements of 10 CFR 50.363, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the desigr objective given in Section II.D of Appendix I to 10 CFR Part 50.
The specified limits governing the use of appro-priate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I,10 CFR Part 50, for liquid effluents.
3/.4/11.1.4 LIQUID HOLDUP TANKS The tanks listed in this specification include all those outdoor radwaste tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.
Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20, Appendix B, Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.
3/4.11.2 GASE0US EFFLUENTS 3/4 11.2.1 DOSE RATE This specification is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents from the site will be within l
the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS.
The annual dose limits are the dose 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 result in the exposure of a MEMBER OF THE PUBLIC 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 20.106(b)(1)).
For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the accupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY.
Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM.
The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/ year to the total body or to less than or equal to 3000 mrems/ year to the skin.
These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to les than or equal to 1500 mrems/ year.
This specification applies to the release of radioactive materials in gaseous effluents from all reactors at the site.
'l LIMERICK - UNIT 1 B 3/4 11-2 Amendment No. 26
' ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT covering all sampling locations ke3ed to a table giving distances and directions from the centerline of the reactor plant; the results of licensee participation in the Interlaboratory Comparison Program, required by Specification 3.12.3; discussion of all deviations from the Sampling Schedule of Table 4.12.1-1; and discussion of all analyses in which the LLD required by Table 4.12.1-1 was not achievable.
SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT *
- 6. 9.1. 8 Routine Semiannual Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of operation shall be sub-mitted within 60 days after January 1 and July 1 of each year.
The period of the first report shall begin with the date of initial criticality.
The Semiannual Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the facility as outlined in Regulatory Guide 1.21, " Measuring,
'Evsluating, and Reporting Radioactivity in Solid Wastes and Releases of Radio-active Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof.
The Semiannual Radioactive Effluent Release Repnrt to be submitted 60 days after January 1 of each year shall include an annual summary of hourly meteorological data collected over the previous year.
This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direc-tion and atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributions of wind speed, wind direction, atmospheric stability.** This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year.
This same report shall also include an assessment of the radiation doses from radioactive liquid and gase-ous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY (Figures 5.1.3-la and 5.1.3-1b) during the report period.
All assump-tions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports.
The assessment of radiation doses shall be performed in accordance with the methodology and parameters of the OFFSITE DOSE CALCULATION MANUAL (ODCM).
- A single submittal may be made for a multiple unit station.
The submittal should combine those sections that are common to all units at the station.
- In lieu of submission with the first half year Semiannual Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.
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LIMERICK - UNIT 1 6-17 Amendment No. 26 1
ADMINISTRATIVE CONTROLS SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT (Continued)
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The Semiannual Radioactive Effluent Release Report to be submitted 60 days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from reactor. releases and other nearby uranium fuel cycle sources (including doses from primary offluent path-i ways and direct radiation) for the previous calendar year to show conformance l
with 40 CFR Part 190, Environmental Radiation Protection Standards for Nuclear Power Operation.
Acceptable methods for calculating the dose contribution from i
liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev.1, October 1977.
The Semiannual Radioactive Effluent Release Reports shall include the following information for each type of solid warte (as defined in 10 CFR Part 61) shipped i
offsite during the report period:
a.
Container volume, b.
Total curie quantity (specify whether determined by measurement or l
- estimate, Principal radionuclides (specify whether determined by measurement c.
or estimate),
d.
Source of waste and processing employed (e.g., dewatered spent resin, compacted dry Gaste, evaporator bottoms),
Type cf container (e.g., LSA, Type A, Type B, Large Quantity), and e.
f.
SOLIDIFICATION agent or absorbent (e.g., cement; urea formaldehyde).
I The Semianitual Radioactive Effluent Release Reports shall include a list and i
description of unplanned releases from the site t UNRESTRICTED AREAS of radio-i active materials in gaseous and liquid effluents m de during the reporting I
period.
The Semiannual Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the ODCM, as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification 3.12.2.
SPECIAL REPORTS l
6.9.2 Special reports shall be submitted to the Regional Administrator of the i
Regional Office of the NRC within the time period specified for each report.
1 LIMERICK - UNIT 1 6-18