ML20212R582

Amend 102 to License DPR-40,revising Tech Specs by Deleting short-term Reporting Requirements for Primary Coolant Specific Activity Levels

ML20212R582
Person / Time
Site:	Fort Calhoun
Issue date:	01/20/1987
From:	Thadani A Office of Nuclear Reactor Regulation
To:
Shared Package
ML20212R575	List: ML20212R573 ML20212R582 ML20212R590
References
GL-85-19, TAC-63186, NUDOCS 8702020720
Download: ML20212R582 (7)

Text

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{ g NUCLEAR REGULATORY COMMISSION t j wAsmNGTON, D. C. 20065

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OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.102 License No. DPR-40

1. The Nuclear Regulatory Comission (the Comission) has found that:

A. The application for amendment by the Omaha Public Power District

(':he licensee) dated October 23, 1986, complies with the standards a*d 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;

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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.

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8702020720 870120 PDR ADOCK 05000285 p PDR

2. Accordingly, Facility Operating License No. DPR-40 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8. of Facility Operating License No.

DPR-40 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.102, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY C0W.ISSION A

Asho C. Thadani, Director PWR roject Directnrate #8 Division of PWR Licensing-B

Attachment:

Changes to the Technical Specifications Date of Issuance: January 20, 1987 t

l ATTACHMENT TO LICENSE AMENDMENT NO.102 FACILITY OPERATING LICENSE NO. DPR-40 DOCKET NO. 50-285 Revise Appendix "A" Technical Specifications as indicated below. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

Remove Pages Insert Pages 2-8 2-8 2-9 2-9 5-16 5-16 5-17 5-17

2.0 LIMITING CONDITIONS FOR OPERATION 2.,1 Reactor Coolant System (Continued) 2.1.3 Reactor Coolant Radioactivity Applicability Applies to the radioactivity of the reactor coolant.

Objective To ensure that the reactor coolant radioactivity is maintained at a level connensurate with the occupational and public safety.

Specification (1) The radioactivity of the reactor coolant shall be limited to:

a. 1 1.0 pCi/gm DOSE EQUIVALENT I-131, and

b. 1 100/ifpCi/gm ,

(2) With the radioactivity of the reactor coolant >1.0 uCi/gm DOSE I EQUIVALENT I-131 for more than 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> during one continuous time interval or exceeding 60 pCi/gm, be in at least H0T SHUTDOWN with Tavg <536 F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

(3) With the radioactivity of the reactor coolant > 100/E pCi/gm, be I in at least HOT SHUTDOWN with Tavg < 536*F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. l (4) With the radioactivity of the reactor coolant >l.0 pCi/gm DOSE I EQUIVALENT I-131, perform the sampling and analysis requirements of items 1.(a)(2)(ii) and 1.(b)(2)(i) of Table 3-4 until the radioactivity of the reactor coolant is restored to within its limits. Data pursuant to Specification 5.9.4.b.l.(e) for the Annual Report shall be compiled as follows:

a. 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

b. Purification System flow histcry 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.

c. The time duration when the radioactivity of the reactor coolant exceeded 1.0 uCi/gm DOSE EQUIVALENT I-131.

d. 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 radiciodine activity was reduced to less than the limit. Each result should contain the date and time of sampling and the radiciodine concentrations.

Amendment No. ?$,$/,102 2-8

2.0 LIMITING CONDITIONS FOR OPERATION 2,1 Reactor Coolant System (Continued) 2.1.3 Reactor Coolant Radioactivity (Continued)

e. Graph of the I-131 concentration and one other radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level.

Basis The limitations on the radioactivity of the reactor coolant ensure that the resulting 2-hour doses at the site boundary will be well within the limits of 10 CFR Part 100 following a steam generator tube rupture accident in conjunction with an assumed steady state primary-to-secondary steam generator leakage rate of 1.0 GPM and a concurrent loss of offsite power.

Permitting operation to continue for limited time periods with the reactor coolant's radioactivity levels >1.0 pCi/gm DOSE EQUIVALENT I-131, but < 60 Ci/gm, accommodates possible iodine spiking phenomenon which may occur following changes in thernal power.

Reducing Tavg to < 536 F prevents the release of radioactivity should a steam generator tube rupture, since the saturation pressure of the reactor coolant is below the lift pressure of the atmospheric steam relief valves. The surveillance requirements provide adequate assurance that excessive radioactivity levels in the reactor coolant will be detected in sufficient time to take appropriate corrective action (s).

References i

USAR, Section 11.11.3 USAR, Section 14.14 I

Amendment No. $0,67, 102 2-9

j.

• i 5.9.4 Unique Reporting Requirements (Continued)

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j ~,, a. Radioactive Effluent Release Report (Continued) .

1 i releases of effluents shall be used for determining the gaseous l~ pathway doses. The assessment of radiation doses shall be performed

[ in accordance with the Offsite Dose Calculation Manual (0DCli).

The radioactive effluent release re ort shall include any changes (I) to the Process Control Program (PCP or to the Offsite Dose Calcula-

> tion Manual (0DCM) made during the reporting period. A level of i detail comensurate to the significance of the change will be provided.

b. Radiological Environmental Operating Reports ,

l j 1. Annual Report 4

l An annual report containing the data taken in the radiological environmental monitoring program, in accordance with the ODCM, for the previous calendar year of operation shall be submitted prior to May 1 of each year. The content of the report shall include:

f (a) Summarized and tabulated results of the radiological J environmental surveillance activities following the l format of Regulatory Guide 4.8, Table 1. In the event

.that some results are not available, 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.

(b) Interpretations and statistical evaluation of the results, including an assessment of the observed impacts of the plant operation on the enviror. ment.

(c) The results of participation in the Interlaboratory Comparison Program.

l (d) The results of land use survey required by Specifica-tion 3.11(3).

! (e) The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 2.1.3. 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; j t l (1) These changes can be initiated either by the licensee (implementa-l tion: subject to review by the PRC) or by the Comission (imple-mentation: subject to their applicability to the Fort Calhoun Station design, review by the PRC and followed by a review by the SARC).

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l 5-16 Amendment No. 86,102 e i

5.9.4 Unique Reporting Requirements (Continued)

b. Radiological Environmental Operating Reports (Continued)

1. Annual Report (Continued)

(2) Results of the last isotopic analysis for radioiodine perfonned 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 the limit. Each result should include date and time of sampling and the radiciodine concentrations; (3) Purification 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 radiciodine limit.

l 2. Non-Routine Report If a confirmed measured radionuclide concentration in an environmental sampling medium average over any calendar quarter sampling period exceeds the reporting level referenced in Table 3-9, Footnote 2, and if the radio-activity is attributable to plant operation, a written report shall be submitted to the Commission within 30 days from the end of the quarter.

The report shall include an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous result.

5-17 Amendment No. 9,79,gg,102