ML17279A174
| ML17279A174 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 03/31/1987 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17279A175 | List: |
| References | |
| TAC-61641, NUDOCS 8704060071 | |
| Download: ML17279A174 (10) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 WPPSS NUCLEAR PROJECT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
39 License No. NPF-21 1.
The Nuclear Regulatory Commission (the Comnission or the NRC) has found that:
A.
The application for amendment filed by the Washington Public Power Supply System (the Supply System, also the licensee),
dated May 27, 1986, comp'lies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the CoIImission's regulations set forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations o< the CoIITIIission; 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 CoIWIIission'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 Facility Operating License No.
NPF-21 is hereby amended to read as follows:
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 39, and the Environmental Protection Plan contained in Appendix 8 are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
8704060071 870331 PDR ADOCK 05000397,'l.
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This amendment is effective as of the date of issuance FOR THE NUCLEAR REGULATORY COMMISSION
Enclosure:
Changes to the Technical Specifications Elinor G ~ Adensam, Director BWR Project Directorate No.
3 Division of BWR Licensing Date of Issuance:
March 3l
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ENCLOSURE TO LICENSE AMENDYENT NO.
39 FACILITY OPERATING LICENSE NO.
NPF-21 DOCKET NO. 50-397 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are identi,ied by Amendment number and contain vertical lines indicating the area of change.
REMOVE 3/4 4-15'/44-16 B 3/4 4-3 6-17 INSERT 3/4 4-15 3/4 4-16 B 3/4 4-3 6-17
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REACTOR COOLANT SYSTEM 3/0.4. 5 SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.5 The specific activity of the primary coolant shall be limited to:
b.
Less than or equal to 0.2 microcurie per gram DOSE E(UIVALENT I-131, and Less'than or'qual to 100/E microcuries per gram.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, 3, and 4.
ACTION:
a.
In OPERATIONAL CONDITION 1, 2, or 3 with the specific activity of the primary coolant; 1.
Greater than 0. 2 microcurie per gr am DOSE EQUIVALENT I-131 but less than or equal to 4 microcuries per gram, DOSE E(UIVALENT 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 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 its limit.
WASHINGTON NUCLEAR " UNIT 2 3/4 4-15 Amendment No.
39
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REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION Continued ACTION:
(Conti nued) c.
In OPERATIONAL CONDITION 1 or 2, with:
2.
3.
THERMAL POWER changed by more than 15K 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 The off-gas level, at the SJAE, increased by more than 15,000 microcuries per second 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 less than 100,000 microcuries per second, or The off-gas level, at the SJAE, increased by more than 15K 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 RE UIREMENTS 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.
"Not applicable during the startup test program.
WASHINGTON NUCLEAR - UNIT 2 3/4 4-16 Amendment No. 39
REACTOR COOLANT SYSTEM BASES 3/4. 4. 5 SPECIFIC ACTIVITY
/
The limitations on the specific activity of the primary coolant ensure that the 2-hour 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 Part 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 conserva-tive 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 microcurie per gram DOSE EQUIVALENT I-131, but less than or equal to 4.0 micro-curies per gram DOSE E(UIVALENT I-131, accommodates possible iodine spiking phenomenon which may occur following changes in THERMAL POWERS 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 coolant will be detected in sufficient time to take corrective action.
WASHINGTON NUCLEAR - UNIT 2 8 3/4 4-3 Amendment No.
ADMINISTRATIVE CONTROLS Y%
ANNUAL REPORTS (Continued) 6.9. 1.5 Reports required on an annual basis shall include:
a.,
A tabulation on an annual basis of the number of station, utility, and other personnel (including'ontractors) receiving exposures greater than 100 mrems/yr and their associated man-rem exposure according to work and job functions" (e.g.,
reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance
[describe maintenance],
waste processing, and refueling).
The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), or film badge measurements.
,Small exposures totalling less than 20K of the individual total dose need not be accounted for.
In the aggregate, at least 80K of the total whole-body dose received from external sources should be assigned to specific major work functions; and b.
Documentation of all challenges to main steam line safety/relief valves.
The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.5.
The following information shall be included:
(1) Reactor 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 analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit.
Each result should include date and time of sampling and the radioiodine concentrations; (3) Cleanup 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 concentration in microcuries per gram as a function of time for the duration 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.
MONTHLY OPERATING REPORTS 6.9. 1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regulatory Commission, Washington, D.C.
- 20555, with a copy to the Regional Administrator of the Regional Office of the
- NRC, no later than the 15th of each month following the calendar month covered by the report.
REPORTABLE OCCURRENCES 6.9. 1.7 DELETED PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP 6, 9. 1. 8 DELETED This tabulation supplements the requirements of f20.407 of 10 CFR Part 20.
WASHINGTON NUCLEAR - UNIT 2 6-17 Amendment No.
39