ML20237L506
| ML20237L506 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 08/31/1987 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20237L509 | List: |
| References | |
| TAC-64865, TAC-64866, NUDOCS 8709080433 | |
| Download: ML20237L506 (8) | |
Text
UNITED STATES
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PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-275 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.18 License No. DPR-80 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Pacific Gas & Electric Company (thelicensee)datedOctober 29, 1986 complies with the standards and requirements of the Atomic Energy Act af 1954, as amended (the Act), and the Comission's rules and regu'lations 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 Comission; C.
Thereisreasonableassurance(i)thattheactivitiesauthorized 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; D.
The issuance of this amendment will not be inimical to the common defense and recurity 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 Comission's regulations and all applicable requirements have been satisfied.
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license-amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-80 is hereby amended to read as follows:
(2)TechnicalSpecifications The Technical-Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 18, are hereby incorporated in the license.
Pacific Gas & Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated'in specific license conditions.
3.
This license amendment becomes effective at the date of its issuance.
FOR THE NU.: LEAR REGULATORY COMMISSION M7.
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George W. Knighton, Director sP roject Directorate V P
l Division of Reactor Projects - III, l
IV, V and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: August 31, 1987 l
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i PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLINT, UNIT 2 DOCKET N0. 50-323 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 17 License No. DPR-82 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Pacific Gas & Electric Company (thelicensee)datedOctober 29, 1085 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; 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
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conducted in compliance with the Comission's regulations; D.-
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safaty of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all epplicable requirements have been satisfied.
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2.
'Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-82 is hereby amended to.?ad as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.
17, are hereby incorporated in the license..
Pacific Gas & Electric Company shall operate the facility in q.
accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.
3.
This license amendment becomes effective at the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION M
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p George W. Knighton, Director D roject Directorate V P
Division of Reactor Projects - III, IV, V and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 31, 1987 j
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August 31, 1987
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l ATTACHMENT TO LICENSE AMENDMENT N05.18 AND 17 FACILITY OPERATING LICENSE NOS. DPR-80 AND DPR-82 DOCKET NOS. 50-275 AND 50-323 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.
Remove Insert 3/4 4-25 3/4 4-25 3/4 4-26 B 3/4 4 B 3/4 4-5 6-17 6-17
REACTOR COOLANT SYSTEM 3/4.4.8 SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 4.8 The specific activity of the reactor coolant shall be limited to:
a.
Less than or equal to 1 microcurie / gram DOSE EQUIVALENT I-131, and b.
Less than or equal to 1006 microcuries/ gram of gross radioactivity.
APPLICABILITY:
MODES 1, 2, 3, 4, and 5.
A_CTION:
MODES 1, 2, and 3*:
a.
With the specific activity of the reactor coolant greater than 1 microcurie / 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 exceeding the limit line shown on Figure 3.4-1, be in at least HOT STANDBY with T less than 500 F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; and avg With the sp/ gram of gross radioactivity, be in at ieast HOT STANDBY ecific activity of the reactor coolant greater than 100/E b.
microcuries with T,yg less than 500 F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
MODES 1, 2, 3, 4, and 5:
With the specific activity of the reactor coolant greater than 1 micro-curie / gram DOSE EQUIVALENT I-131 or greater than 1004 microcuries/ gram of gross radioactivity, perform the sampling and analysis requirements of Item 4.a) of Table 4.4-4 until the specific activity of the reactor coolant is restored to within its limits.
SURVEILLANCE REQUIREMENTS l
4.4.8 The specific activity of the reactor coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-4.
- With T greater than or equal to 500 F.
avg DIABLO CANYON - UNITS 1 & 2 3/4 4-25 Amendment Nos.18 and 17 (next page is 3/4 4-27)
REACTOR COOLANT SYSTEM BASES 3/4.4.7 CHEMISTRY The limitations on Reactor Coolant System chemistry ensure that corrosion of the Reactor Coolant System is minimized and reduces the potential for Reactor Coolant System leakage or failure due to stress corrosion.
Maintaining the chemistry within the Steady-State Limits provides adequate corrosion protection to ensure the structural integrity of the Reactor Coolant System over the life of the plant.
The associated effects of exceeding the oxygen, chloride and fluoride limits are time and temperature dependent.
Corrosion studies show that operation may be continued with contaminant concentration levels in excess of the Steady-State Limits, up to the Transient Limits, for the specified limited time intervals without having a significant effect on the structural integrity of the Reactor Coolant System.
The time interval permitting continued operation within the restrictions of the Transient Limits provides time for taking corrective actions to restore the contaminant concen-trations to within the Steady-State Limits.
The Surveillance Requirements provide adequate assurance that concentrations in excess of the limits will be detected in sufficient time to take corrective action.
3/4.4.8 SPECIFIC ACTIVITY The limitations on the specific activity of the reactor coolant ensure that the resulting 2-hour doses at the SITE BOUNDARY will not exceed an appro-priately small fraction of 10 CFR Part 100 dose guideline values following a steam generator tube rupture accident in conjunction with an assumed steady-state reactor-to-secondary steam generator leakage rate of 1 gpm. The values for the limits on specific activity represent limits based upon a parametric evaluation by the NRC of typical site locations. These values are conservative in that specific site parameters of the Diablo Canyon site, 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 reactor coolant's specific activity greater than 1 micro-curie / gram DOSE EQUIVALENT I-131, but within the allowable limit shown on Figure 3.4-1, accommodates possible iodine spiking phenomenon which may occur following changes in THERMAL POWER. Operation with specific activity levels exceeding 1.0 microcurie / gram DOSE EQUIVALENT I-131 but within the limits shown on Figure 3.4-1 should be limited since the activity levels allowed by Figure 3.4-1 increase the 2-hour thyroid dose at the SITE BOUNDARY by a factor of up to 20 following a postulated steam generator tube rupture.
1 DIABLO CANYON - UNITS 1 & 2 B 3/4 4-5 AMENDMENT N05.18 and 17
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ADMINISTRATIVE CONTROLS ANNUAL REPORTS (Continued)
J rem exposure according to work and job functions,* e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance l
(describe maintenance), waste processing, and refueling.
The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or I
film badge measurements.
Small exposures totalling less than 20% of the i
individual total dose need not be accounted for.
In the aggregate, at least L
80% of the total whole body dose received from external sources shall be assigned to specific major work functions.
The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.8 will be included in the annual report.
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 for radioiodine performed prior to exceeding the limit, results of 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 j
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 concentration in microcuries per gram as a function of time for the duration of specific activity above the steady-state level; and (5) the time duration when the specific activity of the primary coolant exceeded the radioiodine limit.
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT **
- 6. 9.1. 5 Routine Annual Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year.
The initial report shall be submitted prior to May 1 of the year following initial criticality.
The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment.
The reports shall also include the results of land use censuses required by Specification 3.12.2.
The Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in tables and figures in the ERMP as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position Revision 1, November 1979.
In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.
The missing data shall be submitted as soon as possible in a supplementary report.
- This tabulation supplements the requirements of 10 CFR 20.407.
- A single submittal may be made for a multiple unit plant.
DIABLO CANYON - UNITS 1 & 2 6-17 AMENDMENT N05.18and 17
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