ML20086Q770

Proposed Tech Specs Consistent W/Revised Regulations of 10CFR20

ML20086Q770
Person / Time
Site:	Waterford
Issue date:	07/25/1995
From:	ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20086Q761	List: ML20086Q758 ML20086Q770
References
NUDOCS 9507280186
Download: ML20086Q770 (6)

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-RADIDACTIVE EFFLUENTS l

L1001D HOLOUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each of the following i unprotected outdoor tanks shall be limited to less than or equal to 7.85 x 10 4 4' W l

-W 2-curies,* excluding tritium and dissolved or entrained noble gases. For outside l temporary storage tanks, the curie content shall be limited such that a rupture will not

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result in exceeding 10 CFR Part 20 limits at the UNRESTRICTED AREA boundary. '

a. PWST ,

b. Outside temporary tank l l

l APPLICABILITY: At all times.

ACTION:

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a. With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank. within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, and describe the '  !

events leading to this condition in the next Annual Radioactive Effluent Release Report, i

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS -

4,11.1.4 The quantity of radioactive material contained in each of the above listed  !

tanks shall be determined to be within the above limit by, analyzing a representative j sample of the tank's contents at least once per 7 days when radioactive materials are i being added to the tank. l

• B r ~* On 90! t:d cp rit: :nd :n "M Of 2 - 104 ;ff /d C=f r 127 ,

^~ "v: M t, 10 CF" Part 20,.^g end?" 9. T d k !!.

• Based _on__80%__ tank _capac,ity_and M-times-the_ effluent concentration (EC) of 1.0. x .10j C1/.4,..Ces.iq.1137 equivalent,__10CFR_Part20,_AppendixB, i Table 2. Column 2. l 1

l WATERFORD - UNIT 3 3/4 11-8 Amendment No. 84 9507280286 950725 PDR ADOCK 05000382 i P PDR j

i 3/4.11. RADIGACTIVE CFFLUENTS BASES 3/4.11.1 LIQUID EFFLUENTS 3/4.11.1.1 This section deleted.

3/4.11.1.2 This section deleted.

3/4.11.1.3 This section deleted.

3/4.11.1.4 LIQUID HOLDUP TANKS The tanks listed in this specification include all those outdoor radwaste tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the 1 Liquid rRadwaste tTreatment SSystem.

Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting concentrations would be less than-10-t4mes the values given in limits-of-10 CF", Prt 20, Appendix B. Table.44-2, Column 2. to 10 CFR 20.100120.2402 at the nearest potable water supply and the nearest surface water supply in an UNRESTRICTED AREA.

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WATERFORD - UNIT 3 B 3/4 11-1 Amendment No. 68 l

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ADMINISTRATIVE CONTROLS 6.9 REPORTINGRE_QUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10. Code of Federal Regulations, the following reports shall be submitted to the Regional Administrator of the Regional Office of the NRC unless otherwise noted.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an Operating License. (2) amendment to the license involving a planned increase in power level. (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program. (2) 90 days 'ollowing resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.

If the startup report does not cover all three events (i.e., initial criticality.

completion of startup test program, and resumption or commencement of commercial operation), supplementary reports shall be submitted at least every 3 months until all three events have been completed.

ANNUAL REPORTS 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shali be submitted prior to March 1-31 of each year. The initial report shall be submitted prior to March 1-31 of the year following initial criticality.

The results of specific activity analysis in which the primary coolant exceeded the  ;

limits of Specification 3.4.7 shall be submitted annually in accordance with the I aforementioned time frame. The following information shall be included:

I (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:

(2) Results of the last isotopic analysis for radiciodine performed prior to l exceeding the limit, results of analysis while limit was exceeded REVIEWERS NOTE : THE FOOTNOTE BELOW HAS BEEN H0VED TO PAGE 6 17a i

• This tablation-supplements the requirements of 20.'07 of 10 CP Part 20 l WATERFORD - UNIT 3 6-17 AMENDMENT NO. 8 j

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e ADMINISTRATIVE CONTROLS [

ANNUAL REPORTS (Continued) and results of one analysis after the radio iodine activity was reduced to less than limit. Each result should include date and ti:. of sampling and 1 the radio iodine concentrations; a r

, (3) Clean-up 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 I which the limit was exceeded, (4) Graph of the 1-131 concentration and one other radio iodine isotope concantration in micro curies per gram as a function of time for the i duration of the specific activity above steady-state level; and 1

(5) The time duration when the specific activity of the primary coolant 'l exceeded the radio iodine limit.

6.9.1.v Reports required on an annual basis shall be submitted prior to liarch 31 of each y_ ear and include a tabulation on an annual basis of the number of station. utility, and other personnel (including contractors), for whom_ monitor _ing.was_ performed cequired t receiving an annual deep dose equivalent exposures greater than 100 mremfyr and the,.;1r associated . collective deep dose.,eguivalent (reported in person rem) m.n-rem-exposure according to work and job functions.,* (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance [descrit,e maintenancu], 3 waste processing, and refueling). The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescence dosimeter (TLD) or film badge l  !

measurements. Small exposures totaling less than 20% of the individual total dose need j not be accounted for. In the aggregate, at least 80% of the total . deep dose equivalent i received whole.cody dose from external sources should be assigned to specific major work l functions.  !

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• This_ tabulation supplements the requirements of 10 CFR 20.2206_of 10 CFR Part 20. ]

. WATERFORD UNIT 3 .6-17a AMENDMENT NO. 8 j

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I ADMINISTRATIVE CONTROLS RECORD RETENTION (Continued)

1. Records of quality assurance activities required by the 0A Manual.

J. Records of reviews performed for changes made to procedures or equipment or ,

reviews of tests and experiments pursuant to 10 CFR 50.59. '

k. Records of meetings of the PORC and the SRC. .

1. Records of the service lives of all hydraulic and mechanical snubbers - ,

required by Specification 3.7.8 including the date at which the service i life commences and associated installation and maintenance records.

m. Records of secondary water sampling and water quality. i t

n. Records of audits performed under the requirements of Specification i 6.5.2.8.  !

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o. Records of analyses required by the radiological environmental monitoring I program that would permit evaluation of the accuracy of the analysis at a later date. This should include procedures effective at specified times and 0A records showing that these procedures were followed, f

p, Records of reviews performed for changes made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.

6.11 RADIATION PROTECTION PROGRAM j 6.11.1 Procedures for personnel radiation protection shall be prepared consistent with j the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.  ;

6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph >

20J03(c)Ghef 10 CFR Part 20.1601. each high radiation area in which the intensity of radiation is greater than 100 mrem /h but less than 1000 mrem /h shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by j requiring issuance of a Radiation Work Permit (RWP)*. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or j; mo?e of the following:

a. A radiation monitoring device which continuously indicates the radiation i dose rate in the area. )

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• Health physics personnel or personnel escorted by health physics personnel shall be  ;

exempt from the RWP issuance requirement during the performance of their assigned i radiation protection duties, provided they are otherwise following plant radiation j protection procedures for entry into high radiation areas. i WATERFORD - UNIT 3 6-22 AMENDMENT NO. 68 l

. J ADMINISTRATIVE CONTROLS ,

HIGH RADIATION AREA (Continued)

b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.

Entry inte such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them,

c. A health physics qualified individual (i.e., qualified in radiation ,

protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Radiation Protection Superintendent-Nuclear in the RWP.

6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose greater than 1000 mrems but less than 500 Rads

• shall be provided with l locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or health physics supervision / designee. Doors shall remain locked except during periods of access by l personnel under an approved RWP which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area. For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose in excess of 1000 mrems but less then 500 Rads

• that are located within large areas, such as PWR containment. where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around tra individual areas, then that area shall be roped off conspicuously posted and a flashing light shall be activated as a warning device. In lieu of the stay time specification of the RWP, direct or remote (such as use of closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.

6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.

6.13.2 Licensee-initiated changes to the PCP:

a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3p. This documentation shall contain:

1. Sufficient information to support the change together with the appropriate analyse; or evaluation justifying the change (s) and

• Heasurement made at 18-indes30 centireters from the radiation source of-radioactivity, or from any surface that the radiationfenetrates.

WATERFORD - UNIT 3 6-23 AMENDMENT NO. 68