Text

Amend 104 to License NPF-3,revising Tech Specs to Change Reporting Requirements for Primary Coolant Iodine Pikes from short-term Rept to Be Added in Annual Operating Rept & Delete Shutdown Requirement
	ML20238E096
Person / Time
Site:	Davis Besse
Issue date:	09/08/1987
From:	Virgilio M; Office of Nuclear Reactor Regulation
To:	;
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ML20238E097	List: ML20238E096;
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	NUDOCS 8709140135
	Download: ML20238E096 (11)
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UNITED STATES 3'

NUCLE AR REGULATORY COMMISSION t y.

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oyv y TOLEDO EDISON COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY l

DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.104 License No. NPF-3 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by the Toledo Edison Company and The Cleveland Electric Illuminating Company (the licensees) dated March 17, 1987, complies with the standards and 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; 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 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

}

The issuance of this amendment is in accordance with 10 CFR Part 51 E.

of the Commission's regulations and all applicable requirements have been satisfied.

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. NPF-3 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendices A'and B, as revised through Amendment No.104, are hereby incorporated in the license.

The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.

8709140135 870900' ADOCK 0%g6 DR

3.

This license amendment is effective as of its date of issuance and shall be implemented not later than October 8,1987 FOR THE NUCLEAR REGULATORY COMMISSION Martin)DirectorateIII-1. Virgilio, Director Project Division of Reactor Projects - III, IV, V

& Special Projects

Attachment:

Changes to the Technical Specifications Date of Issuance:

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e ATTACHMENT TO LICENSE AMENDMENT NO. 104 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 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.

The corresponding overleaf page(s) are a' Iso provided to maintain document completeness.

Remove Insert

~3/4 4-20 3/4 4-20 3/4 4-21 3/4 4-21 B 3/4 4-6 B 3/4 4-6 6-15 6-15 6-16 6-16 5

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TABLE 4.4 ?

REACTOR COOLANT SYSTEM CHEMISTRY LIMITS' SURVEILLANCE REQUIREMENTS po

-SAMPLE AND PARAMETER ANALYSIS FREQUENCY DISSDLVED OXYGEN

At least once each 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months CHLORIDE At least once each 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months FLUORIDE At least once each 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months f

"Not required with T,yg i 250'F.

s DAVIS-BESSE, UNIT 1 3/4 4-19

REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the primary coolant shall be limited to:

a.

$ 1.0 pCi/ gram DOSE EQUIVALENT I-131, and b.

5 100/f pCi/ gram APPLICABILITY: MODES 1, 2, 3, 4 and 5, 1

ACTION:

MODES 1, 2 and 3*,

a.

With the specific activity of the primary coolant > 1.0 l

pCi/ gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval or exceeding the limit line shown on Figure 3.4-1, be in at least HOT ETANDBY with T

< 530 F

""8 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With the specific activity of the primary coolant > 100/E l

pCi/ gram, be in at least HOT STANDBY with T,yg < 530*F within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

MODES 1, 2, 3, 4 and 5:

c With the specific activity of the primary coolant > 1.0 a.

pCi/ gram DOSE EQUIVALENT I-131 or > 100/E pCi/ gram, perform the sampling and analysis requirements of item 4 a) of Table 4.4-4 until the specific activity of the primary coolant is restored to within its limits. For reporting requirements refer to Section 6.9.1.5.c, Annual Operating Report.

SURVEILLANCE REQUIREMENTS 4.4.8 The specific activity of the primary coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-4.

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DAVIS-BESSE, UNIT 1 3/4 4-20 Amendment No. M

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l DAVIS-BESSE, UNIT 1 3/4 4-21 Amendment No.104

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i 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 reduce the potential for Reactor Coolant System leakage or failure due to stress q

corrosion.. Maintaining the chemistry within the Steady State Limits shown on Table'3.4-1'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 concentrations to within the steady State Limits.

The surveillance requirements provide adequate assurance that con-1 centrations in excess of the limits will be detected in sufficient time to'take corrective action.

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3/4.4.8 SPECIFIC ACTIVITY The limitations on the specific activity of the primary coolant ensure that the resulting 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months doses at the site boundary will not exceed an appropriately _ small fraction of the Part 100 Itmit 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.

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 the specific stte para-meters of the site, such as site boundary location and meteorological conditions, were not considered in this evaluation. The NRC is finaliz-ing site specific criteria which will be used as the basis for the reevaluation of the' specific activity limits of this site. This reevaluation may result in higher ifmits.

I DAVIS-BESSE, UNIT 1 B 3/4 4-5

t-REACTOR COOLANT SYSTEM BASES si The ACTION statement permitting POWER OPERATION to continue for limited time periods with the primary coolant's specific activity > 1.0 pCi/ 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 during one continuous time o

interval with specific activity levels exceeding 1.0 pCi/ gram DOSE EQUIVALENT I-131 but within the limits shown on Figure 3.4-1 must be restricted to no more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months since the activity levels allowed by Figure 3.4-1 l

increase the 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months thyroid dose at the site boundary by a factor of up to 20 following a postulated steam generator tube rupture.

Reducing T to < 530 F prevents the release of activity should a steam generator fu6e rupture since the saturation pressure of the primary coolant is below the lift pressure of the atmospheric steam relief valves.

The surveillance requirements provide adequate assurance that excessive specific activity levels in the primary coolant will be detected in suf-ficient time to take corrective action.

Information obtained on iodine spiking will be used to assess the parameters associated with spiking phenomena. A reduction in frequency of isotopic analyses following power changes may be permissible if justified by the data obtained.

3/4.4.9 PRESSURE / TEMPERATURE LIMITS The pressure-temperature limits of the reactor coolant pressure boundary are established in accordance with the requirements of Appendix G to 10

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CFR 50 and with the thermal and loading cycles used for design purposes.

The limitations prevent non-ductile failure during normal operation, including anticipated operational occurrences and system hydrostatic l

tests. The limito also prevent exceeding stress limits during cyclic operation.

The loading conditions of interest include:

1 1.

Normal operations, including heatup and cooldown, 2.

Inservice leak and hydrostatic tests, and 3.

Reactor core operation.

l The major components of the reactor coolant pressure boundary have been analyzed in accordance with Appendix G to 10 CFR 50.

The closure head I

region, reactor vessel outlet nozzles and the beltline region have been identified to be the only regions of the reactor vessel, and consequently of the reactor coolant pressure boundary, that determine the pressure-i s,

temperature limitations concerning non-ductile failure.

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1 DAVIS-BESSE, UNIT 1 B 3/4 4-6 Amendment No.104

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Ie ADMINISTRATIVE CONTROLS

'j ei power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

1/

ANNUAL OPERATING REPORT 6.9.1.4 Annual reports covering the activities of the unit during the

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previous calendar year shall be submitted prior to March 31 of each year. The initial report shall be submitted prior to March 1 of the year following initial criticality.

6.9.1.5 Reports required on an annual' basis shall include:

i a.

A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposuret greater than 100 mrem /yr and their a exposure according to work and job functions, gociated man rem e.g.,

reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (described maintenance), waste processing, and refueling. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.

Small exposures totalling less than 20% of the individual total dose need not be accounted for.

In the aggreFate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

b.

The complete results of steam generator tube inservice inspections (Specification 4.4.5.5.b).

c.

The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.8.

The

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following information shall be included:

(1) Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis 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 1

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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concen-tration and one other radioiodine isotope concentration in 1/

A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.

U This tabulation supplements the requirements of $20.407 of 10 CFR Part 20.

DAVIS-BESSE, UNIT 1 6-15 Ame.ednent No. 9,72,4J,57, 73,FI' W

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l microcuries per gram as a function of time for the duration of thoffspecificactivity.abovethesteady-statelevel;_and(5)The tinit. duration when the specific activity of the primary coolant excee' dad the radiciodine 11mit'.

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'V 6.9.1.6 ' Routi:le reports of operating statistics, shutdown experience and challenges to'the Pressurizer Power Operated Relief Valve (PORV) and the Pressurizer Code' Safety Valves shall'be submitted on a monthly basis to.

-the Director, Office of' Management and Program Analysis, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy'to the Regional Office, to arrive no later than the'15th of each month following the calendar month covered by'the' report.

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'[ DAVIS-BESSE, UNIT 1 6-16 Amendment No. S, II, 93, 104

ML20238E096

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