ML20215L936
| ML20215L936 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 10/23/1986 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20215L940 | List: |
| References | |
| NUDOCS 8610290378 | |
| Download: ML20215L936 (14) | |
Text
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fo, UNITED STATES
!j g,' i NUCLEAR REGULATORY COMMISSION 5 '(,M r
WASHINGTON, D. C. 20555 i
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-373 LA SALLE COUNTY STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 46 License No. NPF-11 1.
The Nuclear Regulatory Commission (the Comission or the NRC) has found that:
A.
The application for amendment filed by the Commonwealth Edison Company (the licensee), dated June 27, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's regulations set forth in 10 CFR Chapter 1; B.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Comission; C.
There i, 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 ccmpliance with the Comission's regulations set forth in 10 CFR Chapter I; 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 reoutrements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in tne enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-11 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 46, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
8610290378 861023 DR ADOCK 0500 3
3.
This amendment is effective upon date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION f
f se - --- -
Llinor G. Adensam, Director BWR Project Directorate No. 3 Division of BWR Licensino
Enclosure:
Changes to the Technical Specifications Date of Issuance:
October 23, 1986
ENCLOSURE TO LICENSE AMENDMENT NO. 46 FACILITY OPERATING LICENSE NO. NPF-11 DOCKET NO. 50-373 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
REMOVE INSERT 3/4 4-13 3/4 4-13 3/4 4-14 3/4 4-14 6-21(a)
B3/4 4-3 B3/4 4-3 l
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REACTOR COOLANT SYSTEM 3/4.4.5 SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.5 The specific activity of the primary coolant shall be limited to:
Less than or equal to 0.2 microcurie per gram DOSE EQUIVALENT a.
I-131, and b.
Less than or equal to 100/E microcuries per gram.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, 3 and 4.
_ ACTION:
In OPERATIONAL CONDITIONS 1, 2 or 3 with the specific activity of a.
the primary coolant; 1.
Greater than 0.2 microcuries per gram DOSE EQUIVALENT I-131 but less than or egeal to 4.0 microcuries per gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time inter-val or greater than 4.0 microcuries per gram DOSE EQUIVALENT I-131, be in at least HOT SHUTOOWN with the main steam line isolation valves closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
2.
Greater than 100/E microcuries per gram, be in at least HOT l
SHUTDOWN with the main steamline isolation valves closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
In OPERATIONAL CONDITIONS 1, 2, 3 or 4, with the specific activity of the primary coolant greater than 0.2 microcurie per gram DOSE EQUIVALENT I-131 or greater than 100 E microcuries per gram, perform the sampling and analysis requirements of Item 4a of Table 4.4.5-1 until the specific activity of the primary coolant is restored to within the limit.
c.
In OPERATIONAL CONDITION 1 or 2, with:
1.
THERMAL POWER changed by more than 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 /> *, or 2.
The off gas level, prior to the holdup line, increased by more than 25,000 microcuries per second in one hour during steady state operation at release rates less than 100,000 microcuries per second, or l
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- Not applicable during the Startup Test Program.
l LA SALLE - UNIT 1 3/4 4-13 Amendment No. 46 l
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REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION (Continued)
ACTION (Continued) 3.
The off gas level, prior to the holdup line, increased by more than 15% in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during steady state operation at release rates greater than 100,000 microcuries per second, perform the sampling and analysis requirements of Item 4b of Table 4.4.5-1 until the specific activity of the primary coolant is restored to within its limit.
SL'RVEILLANCE REQUIREMENTS 4.4.5 The specific activity of the reactor coolant shall be demonstrated to be within the limits by performance of the sampling and analysis program of Table 4.4.5-1.
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l LA SALLE - UNIT 1 3/4 4-14 Amendment No. 46
ADMINISTRATIVE CONTROLS Annual Report (continued)
The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.5 shall be included in the Annual Report along with the following information:
(1) Reac-tor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analy-sis for radiciodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than limit.
Each result should include date and time of sampling and the radioiodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radioiodine isotope concen-tration in microcuries per gram as a function of time for the dura-tion of the specific activity above the steady state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.
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LA SALLE UNIT 1 6-21(a)
Amendment No. 46
REACTOR COOLANT SYSTEM BASES 3/4.4.5 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> thyroid and whole body doses resulting from a main steam line failure outside the containment during steady state operation will not exceed small fractions of the dose guidelines of 10 CFR 100. The values for the limits on specific activity represent interim limits based upon a parametric evaluation by the NRC of typical site locations.
These values are conservative in that specific site parameters, such as site boundary location and meteorological conditions, were not considered in this evaluation.
The ACTION statement permitting POWER OPERATION to continue for limited time periods with the primary coolant's specific activity greater than 0.2 microcuries per gram DOSE EQUIVALENT I-131, but less than or equal to 4.0 microcuries per gram DOSE EQUIVALENT I-131, accommodates possible iodine spiking phenomenon which may occur following changes in THERMAL POWER.
Closing the main steam line isolation valves prevents the release of activity to the environs should a steam line rupture occur outside containment.
The surveillance requirements provide adequate assurance that excessive specific activity levels in the reactor coolai.t will be detected in sufficient time to take corrective action.
LA SALLE-UNIT 1 B 3/4 4-3 Amendment No. 46
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'o UNITED STATES
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20665 0.
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\\' % 4....f COMMONWEALTH EDISON COMPANY DOCKET NO. 50-374 LA SALLE COUNTY STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 28 License No. NPF-18 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Coninonwealth Edison Company (the licensee), dated June 27, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's 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 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 Comission's regulations set forth in 10 CFR Chapter I; 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 Specifica-tions as indicated in the enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-18 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 28, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This amendment is effective upon date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Elinor G. Adensam, Director BWR Project Directorate No. 3 Division of BWR Licensing
Enclosure:
Changes to the Technical Specifications Date of Issuance:
October 23, 1986 l
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ENCLOSURE TO LICENSE AMENDMENT NO. 28 FACILITY OPERATING LICENSE N0. NPF-18 DOCKET NO. 50-374 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
REMOVE INSERT 3/4 4-14 3/4 4-14 3/4 4-15 3/4 4-15 6-21(a)
B3/4 4-3 B3/4 4-3 I
l
REACTOR COOLANT SYSTEM 3/4.4.5 SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.5 The specific activity of the primary coolant shall be limited to:
Less than or equal to 0.2 microcurie per gram DOSE EQUIVALENT a.
I-131, and b.
Less than or equal to 100/E microcuries per gram.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, and 4.
ACTION:
In OPERATIONAL CONDITION 1, 2, or 3 with the specific activity of a.
the primary coolant; 1.
Greater than 0.2 microcurie per gram DOSE EQUIVALENT I-131 but less than or equal to 4 microcurie per gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or greater than 4.0 microcuries per gram DOSE EQUIVALENT I-131, be in at least HOT SHUTDOWN with the main steam line isolation valves closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
2.
Greater than 100/E microcuries per gram, be in at least HOT l
SHUTDOWN with the main steamline isolation valves closed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
In OPERATIONAL CONDITION 1, 2, 3, or 4, with the specific activity of the primary coolant greater than 0.2 microcurie per gram DOSE EQUIVALENT I-131 or greater than 100/E microcuries per gram, perform the sampling and analysis requirements of Item 4a of Table 4.4.5-1 until the specific activity of the primary coolant is restored to within t % limit.
I c.
In OPERA 10NAL CONDITION 1 or 2, with:
1.
THERMAL POWER changed by more than 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 /> *, or 2.
The off gas level, prior to the holdup line, increased by more than 25,000 microcuries per second in one hour during steady state operation at release rates less than 100,000 microcuries per second, or
- Not applicable during the Startup Test Program.
LA SALLE - UNIT 2 3/4 4-14 Amendment No. 28
REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION (Continued)
ACTION:
(Continued) 3.
The off gas level, prior to the holdup line, increased by more than 15% in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during steady state operation at release rates greater than 100,000 microcuries per second, perform the sampling and analysis requirements of Item 4b of Table 4.4.5-1 until the specific activity of the primary coolant is restored to within its limit.
SURVEILLANCE REQUIREMENTS 4.4.5 The specific activity of the reactor coolant shall be demonstrated to be within the limits by performance of the sampling and analysis program of Table 4.4.5-1.
LA SALLE - UNIT 2 3/4 4-15 Amendment No. 28
ADMINISTRATION COMTROLS Annual Report (continued)
The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.5 shall be included in the Annual Report along with the following information:
(1) Reac-tor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analy-sis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than limit.
Each result should include date and time of sampling and the radiciodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other radioiodine isotope concen-tration in microcuries per gram as a function of time for the dura-tion of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radiciodine limit.
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l LA SALLE - UNIT 2 6-21(a)
Amendment No. 28
REACTOR COOLANT SYSTEM BASES 3/4.4.5 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> thyroid and whole body doses resulting from a main steam line failure outside the containment during steady state operation will not exceed small fractions of the dose guidelines of 10 CFR 100.
The values for the limits on specific activity represent interin limits based upon a parametric evaluation by the NRC of typical site locations.
These values are conservative in that specific site parameters, such as site boundary location and meteorological conditions, were not considered in this evaluation.
The ACTION statement permitting POWER OPERATION to continue for limited time periods with the primary coolant's specific activity greater than 0.2 microcuries per gram DOSE EQUIVALENT I-131, but less than or equal to 4.0 microcuries per gram DOSE EQUIVALENT I-131, accommodates possible iodine spiking phenomenon wnich may occur follcwing changes in THERMAL POWER.
Closing the main steam line isolation valves prevents the release of activity to the environs should a steam line rupture occur outside containment.
The surveillance requirements provide adequate assurance that excessive spec,*ic activity levels in the reactor coolant will be detected in sufficient time to take corrective act.an.
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1 LA SALLE UNIT 2 8 3/4 4-3 Amenoment No. 28
_. _ _ _