ML20063H688

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Proposed Tech Specs Changing Frequency of Reports for Radiological Effluents
ML20063H688
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 02/14/1994
From:
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
Shared Package
ML20063H686 List:
References
NUDOCS 9402220123
Download: ML20063H688 (7)
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Text

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ATTACHMENT 3 TO TXX-94044 AFFECTED TECHNICAL SPECIFICATION PAGES (NUREG-1468) REVISED BY ALL APPROVED LICENSE AMENDMENTS l

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9402220123 940214  !

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/%ype /_ov' 6 3 011 ADMINISTRATIVE CONTROLS SECTION E&EE 6.5.3 TECHNICAL REVIEW AND CONTR0LS............................... 6-11 i 6.6 R E PORTABL E EV ENT ACT I 0N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-13 l 6.7 S A F ETY L I M I T V I O LAT I ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-13 6.8 PROCEDURES AND PR0 GRAMS....................................... 6-13 6.9 REPORTING REQUIREMENTS........................................ 6-17 6.9.1 ROUTINE REP 0RTS............................................. 6-17 Startup Report.............................................. 6-17 An n u al Re p o r t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-18 Annggl Radiolog Re ort.......... 6-19 nnual Radioactive Effluent Release ~ Report. . . . . . . . . . . . . 6-19  :

Mon h y at ng eports................................... 6-19 Core Operating Limits Report................................ 6-20 6.9.2 SPECIAL REP 0RTS............................................. 6-22 6.10 RECORD RETENTION............................................. 6-22 6.11 RADIATION PROTECTION PR0 GRAM................................. .6-23  ;

j 6.12 HIGH RADIATION AREA..........................................- 6-23 J l

6.13 PROCESS CONTROL PROGRAM (PCP)................................ 6-25 6.14 0FFSITE DOSE CALCULATION MANUAL (00CM)....................... 6-25 i

COMANCHE PEAK - UNITS 1 AND 2 xvi

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%1n DEFINITIONS MEMBER (S) 0F THE PUBLIC )

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! 1.18 MEMBER (5) 0F THE PUBLIC shall include all persons who are not occupa-  !

i tionally associated with the plant. This category does not include employees j

! of the licensee, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. f This category does include persons who use portions of the site for recre .

ational, occupational, or other purposes not associated with the plant.

OFFSITE DOSE CALCULATION MANUAL 1.19 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology 1 and parameters used in the calculation of offsite doses resulting from radio- -

active gaseous and liquid effluents, in the calculation of gaseous:and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the. Environ-mental Radiological Monitoring Program. The ODCM shall also contain (1) 'the Radioactive Effluent Controls and Radiological. Environmental Monitoring Pro-grams required by Section 6.8.3'and (2) descriptions of the information t at) '

1 in _.in_the_ Ann u alla d i olog i caLED11ronmen t al : Onoratijig,Andy Sri

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nual Rad osctive Effluent Release Reports requirfby Specifications 6.9.1.3 <

and 6.9.1.4. ~~

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OPERABLE - OPERABILITY .

1.20 A system, subsystem, train, component or device shall be OPERABLE or. ,

have OPERABILITY when it is capable of performing its specified function (s),-

and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other. auxiliary equipment that are required for the system, subsystem, train, component, or' device to perform its function (s) are also capable of perforising their related support function (s).

OPERATIONAL MODE - MODE 1.21 An OPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperatura specified in Table 1.2.

PHYSICS TESTS 1.22 PHYSM TESTS shall be those tests performed to measurt the fundamental' nuclear characteristics of the reactor core and related instruentation:.

(1) described in Chapter 14.0 of the FSAR, (2) authorized under the provisions of 10 CFR 54.99, or (3) otherwise approved by the Commission.

PRESSURE BOUIEARY LEAKAGE 1.23 PRESSURE B0UNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a nonisolable fault in a Reactor Coolant System component body, pipe wall, or vessel wall.

COMANCHE PEAK - UNITS 1 AND 2 1-4

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l RADIOACTIVE EFFLUENTS l

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, 3/4.11.1 LIQUID EFFLUENTS i

LIOUID HOLDUP TANKS

  • LIMITING CONDITION FOR OPERATION 3.11.1 The quantity of radioactive material contained in each unprotected outdoor tank shall be limited to less than or equal to 10 Curies, excluding tritium and dissolved or entrained noble gases.-

1 APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive material in_any unprotected outdoor-tank exceeding the above limit,-immediately suspend all additions of- i c w th d e events leading to this condition in the'next @nual- Radioactive Effluent Release.  ;]_ -l Report, pursuant to Speci ca ion 6.9.1.4. '
b. The provisions of Specifications 3.0.3:are not applicable.. -

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l SURVEILLANCE REQUIREMENTS ,

i 4.11.1 The quantity of radioactive material contained in each:of the unprotected outdoor tanks shall be determined to be within the above limit by.

analyzing a representative' sample of the tank's contents ~at least once per-7 days when radioactive materials are being added to the tank'.

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  • Tanks included in this specification'are-those unprotected outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank' 4 contents and that do not have tank overflows and surrounding area drains i

connected to the Liquid Radwaste Treatment System. 1 COMANCHE PEAK - UNITS 1 AND 2 3/4 11-1 a

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RADIOACTIVE EFFLUENTS GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION 3.11.2.2 The quantity of radioactivity contained in each gas storage tank shall be limited to less than or equal to 200,000 Curies of noble gases (considered as Xe-133 equivalent).

APPLICABILITY: At all times.

ACTION: (Units 1 and 2)

a. With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of onte ng t this condition in the next}Sem4Jhnual Radioactive Effluent Release f-Report, pursuant to Specification 6.9.1.4.
b. The provisions of Specifications 3.0.3 are not applicable..

SURVEILLANCE REQUIREMENTS 4.11.2.2 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per 92 days when radioactive materials are being added to the tank.

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i COMANCHE PEAK - UNITS 1 AND 2 3/4 11-3 Unit 1 - Amendment No. 14.

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g iglSTRATIVE CONTROLS l

ANNUAL REPORT 5 (Continued)

b. The results of specific activity analyses in which the primary coolant exceeded the limits of Specification 3.4.7. The following information shall be included: (1) Reactor pcwer 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 (in graphic and tabular format); (2) Results of the last isotopic analysis for radio-iodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radio-iodine' activity was reduced to.less than limit. Each result should include date and time of sampling and the radiciodine concentrations; (3) Clean-up 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 (sci /ge) and one other radioidine isotope concentration.(pC1/gs).as-a function of time for the duration of the specific activity above the i

steady-state level; and (5) The time' duration when the specific activity of the primary coolant exceeded the radiciodine limit.

ANNUAL RADIOLOGICAL ENVIR0pmENTAL OPERATING REPORT

the operation of the unit during the previous calendar year shall be submitted before May I of each year. The report shall include summaries, interpretations, i and analysis of trends of the results of the Radiological Environmental Monitor-ing Program for the reporting period. The' material provided shall be consistent with the objectives outlined in (1) the ODCM, and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix ! to 10 CFR 50.

RADI0 ACTIVE EFFLUENT RELEASE REPORT **

l 6.9.1.4 The b nnua Radioactive Efflue t ee R ering the. '

i operationj g _ P4 e e.. j e_orevious x :t.. ef ei,erette; shall be >

submitt- eac year. The report a suengg;r n= EtTes or radioactive liquid-and g

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t sa nc MahThuant effluents and solid waste released from the unit. The material provided shall bjI be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conforr.ance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR 50.

MONTHLY OPERATIM REPORTS 6.9.1.5 Routlas reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety _ valves,

  • A single submittal may be made for a multiple unit station.
    • A single submittal may be made for a multi-unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall .

specify the releases of radioactive material from each unit. '

COMANCHE PEAK - UNITS 1 AND 2 6-19 i

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. fttfArA ment 9 $ 7)(y-9S oy t l'99 4 of 6 ADMINISTRATIVE CONTROLS 6'.13 PROCESS CONTROL PROGRAM (PCP)

Changes to the PCP:

a.

i Shall be documented and records of reviews performed shall be retained

as required by Specification 6.10.30. This documentation shall contain

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1) i Sufficient information to support the change together with the "

appropriate analyses or evaluations justifying the t.5ange(s) and {

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2) 9 A determination that the change will maintain the 'averall  !

conformance of the solidified waste product to. ex'. sting requirements of Federal, State, or other applicat'le regulations. i

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Shall become effective after review and acceptance b  !

i approval of the Vice President, Nuclear Operations. y the SORC and the j

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! 6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM)- i l Changes to the 00CM: I

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Shall be documented and records of reviews performed shall be reta.ined as required by Specification 6.10.30. ,

} contain: This documentation shall

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Sufficient information to support the change together with the  ;

i appropriate analyses or evaluations justifying the change (s) and i

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2)

A determination that the change will maintain the level of-radioactive effluent control required by 10 CFR 20.106, 40 CFR  !

i 190, 10 CFR 50.36a, and Appendix ! to 10 CFR 50 and not adverse l

4 impact the accuracy or reliability of effluent, dose, or:setpoint calculations.

b.

Shall become effective after review and acceptance b i

approval of the Vice President, Nuclear Operations. y the 50RC and the j c.

3 Shall be submitted to the Commission in the form of a complete, L of-the entire 00CM as a part of or concurrent with the 4

adioactive Effluent Release Report for the period of the 1 ich any change to the CDCM was made. Each cha'n identified by markings in the margin of the affected pages,ge shall be clearly  ;

i indicating the area of the page that-was changed, and shall indicate

  • the date (e.g., month / year) the change was implemented. "

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i COMANCHE PEAK - UNITS 1 AND 2 6-25 I

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