ML20245J367

Amend 71 to License DPR-34,revising Provisions in Tech Specs Re Radiological Effluents

ML20245J367
Person / Time
Site:	Fort Saint Vrain
Issue date:	08/14/1989
From:	Weiss S Office of Nuclear Reactor Regulation
To:
Shared Package
ML20245J356	List: ML20245J351 ML20245J367 ML20245J378
References
NUDOCS 8908180012
Download: ML20245J367 (12)

Text

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o UNITED STATES -

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NUCLEAR REGULATORY COMMISSION m

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A PUBLIC SERVICE COMPANY OF COLORADO DOCKET NO. 50-267 FORT ST. VRAIN NUCLEAR GENERATING STATION

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AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.71-License No. DPR-34 l1.

The Nuclear Regulatory Comission (the Cemission) has found that:

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' A.~

The application for amendment by Public Service Company of. Colorado -

-(thelicensee) dated' April 14, 1989,- 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; I

B.

.The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; 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 license amendment will not be inimical to the-co m on defense and security or to the health and safety of the public;

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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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E 8908180012 890814 PDR ADOCK 05000267 l

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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, 9

and paragraph 2.D.(2) of Facility Operating License No. DPR-34 is hereby amended to read as follows:

(2) Technical Spec D eations The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 71, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

'3.

The license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Seymour H. Weiss, Director Non-Power Reactor, Decommissioning and Environmental Project Directorate Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: August 14, 1989 i

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if-ATTACHMENT TO LICENSE AMENDMENT NO.71 TO FACILITY OPERATING LICENSE NO. DPR-34 DOCKET NO. 50-267 Replace the following pages of the Appendix A Technical Specifications with the attached pages as inoicated. The revised pages are identified by amendment number and contain vertical lines indicating the' areas of change.

Remove Insert 8.1-3 8.1-3 8.1-4 8.1-4 8.1-5 8.1-5 8.1-6 8.1-6 8.1-7 8.1-7 8.1-8 8.1-9 8.1-10 8.1-10 8.1-23 8.1-23 8.1-24 8.1-24

Fort Sti Yrain #1

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E Technical Specifications Amendment No. 37,71 Page 8.1-3 d)

Prior to the release of gaseous radioactivity from the gas waste surge tanks, the contents shall. be sampled and analyzed for tritium, and a gamma spectral analysis shall be performed to determine that releases will be in compliance with conditions a) and b).

e)

Under normal operating conditions, tritium from the hydrogen getters shall be disposed of as solid waste on an adsorbent material.

f)

At least one Reactor Building exhaust fan shall be operating whenever releases from the gas waste system are taking place.

g)

Gaseous radioactive effluents released from the plant shall be continuously monitored and recorded.

1)

During power operation and/or a release from the gaseous waste holdup system, one noble gas monitor, one halogen monitor, and one particulate monitor and their associated recorders shall be I

i operable.

If any monitor being relied upon to l

meet this requirement has only a local alarm, the l

monitor shall be checked at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> l

to verify it is not alarming.

If it is alarming i

l the release shall be terminated immediately. Use l

of a noble gas, halogen, or particulate monitor l

having only a local alarm shall be limited to 90 l

days.

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d Fort St. Vrain #1-Technical Specifications-

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Amendment No. U,71 Page 8.I-4

- 2).

If the required halogen monitor or the required

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l-particulate monitor. becomes'. inoperable, power l

operation and/or gaseous' effluent releases from m

'the Reacto.r Building ventilation system. may

'l continue, provided a sample of.th'e' effluent stream l

-is continuously collected. The samples shall 'be l.

obtained at least once per :-seven days. Once, l

~ obtained, the-samples:shall be analyzed within 48 l

hours.

If the recorder becomes inoperable, releases may continue provided-the count rate of each operable-monitor is recorded at least once per four hours.

during actual releases.

l 3)'

If the required noble gas monitor becomes inoperable, gaseous effluent releases from the Reactor Building ventilation system, exclusive of releases from the gas ' waste holdup system, may continue, provided grab samples are taken at least once per. eight hours and these samples are l

analyzed for noble gas activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

If the recorder becomes inoperable, releases may continue provided the count rate of each operable monitor is recorded at least once per four hours duririg actual releases.

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Technical Specifications' it Amendment No. 37,71 Page 8.1-5 1-L

.4)

If the required noble gas monitor becomes; v.

inoperable, gaseous effluent releases from the gas?

waste holdup system may continue, provided$that prior to the release:

- (a) Duplicate samples of the gas waste holdup system contents are analyzed per ELCO 8.1.1.d) and

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(b) At.least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup.

5)-

If the gaseous waste holdup system effluent flow rate measuring devices. or the Reactor Building l

exnaust stack flow rate measuring device become inoperable, releases may continue, provided the flow rate is estimated at least once per four hours. The exhaust stack flow rate is not used in calculating allowable gas waste discharge flow rates; however it can be estimated by observing how many reactor building exhaust fans are operating.

Flow rate from the gaseous waste holdup system can be estimated by performing a pressure decay evaluation.

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Technical Specifications Y

Amendment' No J7,71 Page 8.1-6 6)

If the gas waste header noble gas activity monitor

-becomes' inoperable, gaseous effluent releases-may-

' continue, provided a ' daily grab' sample-is takeb and v

analyzed.within.24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for gamma activity or

• .he effluents are diverted to the gas waste surge tank. _If the' recorder becomes inoperable, releases may continue

, provided the count rate of each operable monitor is.

recorded at.least once'per four hours during actual releases.

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If, during power operation, the steam jet air ejector discharge monitor becomes inoperable, the reactor must

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be shut down within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

If there is indication of a primary to secondary leak. through the steam generator reheater section, a'

grab sample shall be taken at.least once per twelve hours and analyzed for noble gas actiyity within twenty-four hours.

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With less than the minimum required radioactive gaseous

.l effluent monitors operable, return the minimum required i

monitors to operable status within 7 days, and, if I

unsuccessful, the failure to correct the inoperability

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• v Technical Specifications

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Amendment No. p,71-

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.shall.be explained in a Special Report within 14 l.

-days of the event. _This report will outline the l

cause.of'theinoperability,actionstakenandthe ll schedule for restoring the. system to-an operable l

status.

'h)-

The-air dose due to noble.' gases released in ' gaseous effluents at the. unrestricted area will be limited to 5 millirad gamma and 10 millirad beta during any caIendar l:

quarter'and 10 millirad gamma and 20 millirad bete during any calendar year.

In addition, the dose to a member of the public due to I-131, tritium, and radioactive particulate with half-lives longer than eight days in gaseous effluents will be limited to 7.5 millirem to any (frgan during any calendar quarter and '15 millirem to any organ during any calendar year.

1)

The' dose rate due to radioactive materials released in gaseous effluents from the site to unrestricted areas 'shall be limited to the following:

For noble gases - less than or equal to 500 millirems per year to the total body and less than or equal to 3,000 millirems per year to the skin.

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For I-131, for tritium, and for all radionuclides in particulate form with half-lives greater than eight days less than or equal to 1,500 millirems per year to any organ.

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Technical Specifications; 4 ^,4 -

Amendment No.' 37,71 Jf' Page 8.1-9 NOTE:

The channel functional test shall also demonstrate-11-that the Control Room or local alarm annunciation.

l occurs if any of the following conditions exists:

.a 1.

Instrument indicates measured levels above the alarm setpoint.

2.

' Circuit failure.

3.

Instrument indicates a downscale failure.

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The initial channel calibration shall be performed using one or more reference standards certified by the ' National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that-

. participate in measurement assurance activities with NBS. These standards shall permit-calibrating the system over its intended ran'ge of energy and~ measurement.

For subsequent channel calibration, sources that have been related to the initial calibration shall be used.

(Previously 1

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Technical Specifications h

' Amendment' No. 37. 71 q

Page 8.1-10'

(

established

. calibration'

. procedures may be substituted for'this requirement.)

Channel check shall consist of verifying-

indication of -flow during periods: of release.

Channel check shall be made at least once per.

.24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.

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Whenever. a gas waste tank is in service for 7 days, a

. sample from the gas waste tank in service shall be l

obtained and further samples shall be obtained weekly l-thereafter while 'the tank remains in service. A gamma

-l spectral analysis shall be performed on'these samples

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within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

e)

The on-line vent. iodine / particulate monitor filter shall be analyzed for gross alpha activity, gross beta

' activity, and principal gamma emitting nuclides once per week to determine that releases are in compliance with ELCO 8.1.1.a) and b).

Analysis for Sr-89 and Sr-90 will be done when the gross beta activity exceeds l

three times the lower limit of detection.

f)

The on-line vent iodine / particulate monitor iodine cartridge shall be analyzed weekly for I-131 to determine that releases are in compliance with ELCD 8.1.1.b).

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Technical, Specifications y

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Amendment No 37. 71 Page B.1-23 Specification ESR 8.1.2 - Radioactive Liouid'

Effluent, Surveillance Raouirements

{a)':The level alarms and. pump inter 1ocks on the two 1.iquid waste receiver tanks and monitoring' tank shall-be tested once per year.

b)

.The liquid effluent discharge blocking valve shall:be functionally tested prior to.each-release.or once a month, whichever is more frequent.

c)

The activity monitors.'of the liquid effluent disch'arge line and the Gas Waste Compressor Cooling Water System, and the low cooling water blowdown flow switch shall be functionally tested quarterly.

The liquid effluent i

activity monitors shall be source checked prior to each release; channel checked during. each release, and calibrated once per 18 months and following maintenance on the detector system.

The Gas Waste Compressor-Cooling Water System monitors shall be channel checked weekly,: source checked monthly, and calibrated once per 18 months and following maintenance on the detector

system, d)

Flow rate monitors and activity recorders shall be channel checked during each release,.

functionally

~ tested quarterly and calibrated once.per 18 months.

NOTE:

The channel functional test shall also I

demonstrate that Control Room or local. alarm annunciation occurs if any of the following conditions exists:

1.

Instrument indicates measured levels above the alarm setpoint.

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Technical Specifications

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Amendment No. 37,71

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Page 8.1-24 l

l 2.

Circuit failure.

3.

Instrument indica'tes a downscale failure.

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.The initial channel calibration shall be performed using one or more reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate

'in measurement assurance-activities with NBS. These standards shall permit i

calibrating the system over its intended range of energy and measurement.

For subsequent char.nel calibration, sources that have'been related to the initial calibration shall be used.

(Operating plants may substitute previnusly established calibration procedures for this requirement.)

Channel check shall consist of verifying indication of flow during periods of release.

Channel check shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which miaw_.--a

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