ML20197A879

Proposed Tech Specs,Incorporating Revised Reporting Requirements on Primary Coolant Iodine Spikes

ML20197A879
Person / Time
Site:	Fort Calhoun
Issue date:	10/21/1986
From:	OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20197A843	List: ML20197A839 ML20197A861 ML20197A879
References
GL-85-19, TAC-63186, NUDOCS 8610270414
Download: ML20197A879 (4)

Text

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2.0 L"4ITING C0f!DITIONS FOR OPERATION 2.1 Reactor Coolant System (Continued)

W 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 commensurate with the occupational and public safety.

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

a. < 1.0 pCi/cm DOGE EQUIVAL12iT I-131, and

b. < 100/E uCi/tyn

~(2) iltth the radioactivity vi the reactor coolant->1;O ucihrD)SE-EQi1TVALENT-

, -I-131 but-1-60 -uC1/em,-operation ,-to-include-restart-if-shutdown ,.may con .

- t in ue -fo r-up-to-100-hours-cmnu l at i vo-ope rat in g-t ime -unue r -theu e - e i rc um-stances ,-not-to-exceed-800 hours-in-any-consecutive month period.

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( 3) With the radioactivity of the reactor coolant >1.0 pCi/cm DOSE 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 HOT SHUTDOWN with Tayg (5360F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

(h) With the radioactivity of the reactor coolant > 100/E uCi/gm, be in at least HOT SHUTDOWN with T avg < 5360F vithin 6 ho'urs.

(5) With the radioactivity of the reactor coolant >1.0 pCi/gm DOSE EQUIVALENT I-131, perform the sampling and analysis requirements of items 1.(a)(2)(ii) and 1.(b)(2)(1) of Table 3-h until the radioactivity of the reactor coolant is restored to within its limits._.;A-REPORTABLE-0CCURRENCE, pursuant to Specification

~_- 7 5 9.2, shall be" submitted to-the Commission.-This-report-shall f)e ' contain the results of the radioactivity analyses-together-with

' the folloving-information:

S.], 4 6. t /8) 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 c sample in which the limit was exceeded.

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Amendment 23,,6i 2-8 - < -

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ll 2.0 LIMITING CONDITIO!!S FUR OPERATION P.1 Reactor Coolant System (Continued)

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..!.3 ' Reactor Coolant R:utioact.ivity (Cont.inued)

b. Purification System flow history starting h8 hours prior to the first sunple in which the limit van exceeded.

c. The time duration when the radioactivity of the reactor coolant exceeded 1.0 pCi/cm DOGE EQUIVALENT I-131.

I N

l Basis i

The limitations on the radioactivity of the reactor coolant ensure i

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.

1 Permittind power operation to continue for limited time periods with the reactor coolant 's radioactivity levels >1.0 pCi/gm DOSE EQUIVEE!;T I-131, but < 60 uCi/gm, accommodates possible iodine spikinc phenomenon which may occur rolleving chances in thermal power.

Re'ducing Tavg to < 5360F 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 atmoupheric steam relief valves. The surveillance requirements provide rideqwite

_, assurance that excessive radioactivity levels in the reactor' coohtnt i

vill be detected in curricient time to take approprinte corree tiver

, netion(s).

References l- USAR, Section 11.11.3 USAR, Section 14.1h -

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5 9.h Unique Recorting Requirements (Continued)

> a. Radioactive Effluent Release Retort (Continued) releases of effluents shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be per-formed in accordance with the Offsite Dose Calculation Manual (CDCM).

The. radioactive effluent release report shall include any changes (l) l to the Process Control Program (PCP) or to the Offsite Dose i Calculation Manual (ODCM) made during the reporting period. A level of detail commensurate to the significance of the change will l

be provided.

I

b. Radiological Environmental Operating Reports

1. Annual Report }'

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 i prior to May 1 of each year. The content of the report shall j include: l (a) Summarised and tabulated results of the radiological i environmental surveillance activities following the

- 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 supplementan repo rt.

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

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

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

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.m u Pe (1) These changes can be initiated either by the licensee (implementa-tion: subject to review by the PRC) or by the Commission (imple-I centation: subject to their applicability to the Fort Calhoun Station design, review by the PRC and followed by a review by the SARC).

l 5-16 Amendment No. 86

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5.9.h unique Reporting Requirements (Continued)

b. Radiological Environmental Operating Reports (Continued)

2. Iron-Routine Report If a confir=ed measured radionuclide concentration in an j 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.

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