ML20097H417

Corrected Pages 216a21,216a22 & 231 to License DPR-46.Errors Corrected

ML20097H417
Person / Time
Site:	Cooper
Issue date:	01/24/1996
From:	NRC (Affiliation Not Assigned)
To:
Shared Package
ML20096H403	List: ML20096H400 ML20097H417
References
NUDOCS 9601290415
Download: ML20097H417 (3)

Text

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i 3.21 & 4.21 AL1E1 3.21.A & 4.21.A INSTRUMENTATION 3.21.A.1 & 4.21.A.1 Liould Effluent Monitoring j

The radioactive ' liquid effluent 'nstrumentation is provided' to monitor and control, as i

l applicable, thn release of radioactive material in liquid affluents. The OPERABILITY and use j

of these instruments implements the requirements of 10 CFR Part 50, Appendix A, General Design Criteria 60, 63, and 64.

The alarm and/or trip setpoints for these instruments are calculated in the mmner described in the ODAM to assure that the alarm and/or trip will occur before the lim!.t specified in 10 CFR Part 20.1302 is exceeded. Controlofthenormall liquid discharge pathway is assured by station procedures governing locked discharge valves and valve line-up verification.

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-3.21.A.2 & 4.21.A.2 Cameous Effluent Monitoring The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The location of this instrumentation is indicated by a Figure in the ODAM, a simplified flow diagram showing gaseous effluent treatment and monitoring equipment. The alarm / trip setpoints for these instruments shall be calculated in accordance with methods in the ODAM, which have been reviewed by NRC, to ensure that the alarm will occur prior to exceeding the limits of 10 CFR Part 20.

The process monitoring instrumentation includes provisions for monitoring the concentrations of potentially explosive gas mixtures in the augmented offgas treatment system. The OPERABILITY and use of this instrumentation is consistent with the requirements of Ceneral Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

In the event no flow rate measurement device is operable on a gaseous stream, alternative 24-hour estimates are adequate since the system design is constant flow and loss of flow is alarmed in the control room.

3.21.5 & 4.21.8 LIOUID EFFLUENTS 3.21.B.1 & 4.21.B.1 Concentration This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20.1302. Thislimitationprovidesadditionall assurance that the levels of radioactive materials in bodies of water outside the site will-not result in exposures within (1) the Section IV. A guides on technical specifications in Appendix I,10 CFR Part 50, for an individual and (2) the limits of 10 CFR Part 20.1301 and 20.1302(b)(2)(i) to the population. The concentration limit for noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air'(submersion) was ' converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

Since Service Water is not a normal or expected source of significant radioactive release, l l

routine samplig, and monitoring for radioactivity is precautionary. An activity concentra-tion of 3 x 10~ pCi/a1 in Service Water effluent is diluted in the discharge canal to about l 1.5% of the 10 CFR 20 Appendix B Table 2 Column 2 concentration with only one circulating water pump operating.

During normal Station operation the dilution would be even greater.

By monitoring Service Water effluent continuously for radioactivity and by confirmatory l sampling weekly, reasonable assurance that its activity concentration can be kept to a small fraction of the 10 CFR Part 20.1302 limit and within the Specification 3.21.B.2.a limit is l provided.

By monitoring Service Water continuously and liquid radwaste continuously during discharge with the monitor set to alarm or trip before the limit specified in 10 CFR 20.1302 is exceeded, reasonable assurance of compliance with Specification 3.21.B.1.2 is provided.

Verification that radioactivity in liquid effluent averaged only a small fraction of the concentration limit is provided by calculations demonstrating compliance with Specifica-tion 3.21.B.2.a.

9601290415 960124 PDR ADOCK 05000298 P

PDR Amendment No. 49,l'/4

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3.21 & 4.21 RASES (Cont'd) i 3.21.8 & 4.21.5 LIOUID EFFLUENTS (Cont'd) 3.21.B.1 & 4.21.B.1 Concentration (Cont'd) f Compliance with 10CFR Part 20.1302(b)(2)(1) implies that the concentration limit l represented by.10CFR Part 20, Appendix B, Table 2 will be met within a suitable and reasonable averaging time for assessing compliance. That averaging time is dependent upon the resolving time of the measurements or estimates which are used to evaluate compliance.

Assessment of compliance is done by sampling and analysis according to Specification 4.21.B.1.2, by estimating or measuring the maximum release flow and the minimum dilution flow coincident during the period of release represented by the sample, and by computing l the concentration as a fraction of the limit in the UNRESTRICTED area periodically on the l

basis of these data.

3.21.B.2 & 4.21.B.2 Liauid Dose Specifications 3.21.B.2, 3.21.C.2 and 3. 21.C. 3 implement the requirements of 10 CFR Part 50.36a and of 10 CFR Part 50, Appendix I, Section IV.

These specifications state LIMITING CONDITIONS FOR OPERATION (LCO) to keep levels of radioactive materials in LWR l cffluenta as low as is reasonably achievable. Compliance with these specifications will clso keep average releases of radioactive material in effluents at small percentages of the limits specified in 10 CFR Part 20.1301.

SurveillanceRequirementsprovideforthel measurement of releases and calculation of doses to verify compliance with the Specifications. Action statements in these Specifications implement the requirements of 10 CFR Part 50.36(c)(2) and 10 CFR Part 50, Appendix I, Cection IV.A in the event an LCO is not met.

Annual dose limitations stated in Specifications 3.21.B.2, 3.21.C.2, and 3.21.C.3 are not strict limits as used elsewhere in the Technical Specifications (are not cn immediate safety concern) but do obligate NPPD to take the applicable reporting action required in Specifications 3.21.B.2.b, 3.21.C.2.b, or 3.21.C.3.b.

10 CFR Part 50 contains two distinctly separate statements of requirements pertaining to effluents from nuclear power reactors. The first concerns a description of equipment to maintain control over radioactive materials in effluents, determination of design ebjectives, and means to be employed to keep radioactivity in effluents ALARA.

This requirement is stated in Part 50 Section 34a and Appendix I,Section II.

Appendix I,Section III stipulates that conforance with the guidance on design objectives be demonstrated by calculations (since demonstration is expected to be prospective).

The other is a requirement for developing LIMITING CONDITIONS FOR OPERATION in technical l cpecifications. It is stated in 10 CFR Part 50, Section 36a and Appendix I,Section IV.

Both the intent of the Commission and the requirement are clearly stated in the Opinion of the Commission;y relevant paragraphs from that document follow:

Section 50.36a(b) of 10 CFR Part 50 provides that licensees shall be guided by certain considerations in establishing and implementing operating procedures specified in technical specifications which take into account the need for operating flexibility and at the same time ensure that the licensee will exert his best efforts to keep levels of radioactive materials in effluents as low as practicable.

The Appendix I that we adopt provides more specific guidance to licensees in this respect.

Amendment No. 49,174

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6.5.1.C (cont'd) a 1.

A tabulation on an annual basis of the number of station,' utility and other personnel (including contractors) receiving exposures j

greater than 100 mres/yr and their associated man rem exposure 1

i according to work and job functions, e.g., reactor operations and l i

surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), vaste processing, and l

refueling. M dose assignment to various duty functions may be estimatt e S **sti on pocket dosimeter, TLD, or film badge measure-l ments.

smali vaposures totaling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least j

80% of the total ubole body dose received from external' sources shall be assigned to specific major work functions.

2.

A summary description of facility changes, tests or experiments in accordance with the requirements of 10CFR50.59(b). This report may be submitted annually or along with the Updated Safety Analysis Report (UFSAR) updates as required by 10CFR50.71(e).

3.

Documentation of all challenges to relief valves or safety valves.

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D.

Monthly Operating Recort Routine reports of operating statistics, shutdown experience, and a narrative summary of operating experience relating to safe operation of j

the facility, shall be submitted on a monthly basis in the manner j

specified by 10CFR50.4 no later than the 15th of each month following the calendar month covered by the report.

l E.

Annual Radiological Environmental Recort 1.

Routine radiological environmental reports covering the surveil-lance activities related to the Station operation during the previous calendar year shall be submitted to the NRC before May 1 of each year.

2.

The Annual Radiological Environmental Report shall include the following:

4 a.

A summary of doses to a MEMBER OF THE PUBLIC OFFSITE due to Cooper Nuclear Station aqueous and airborne radioactive effluents, calculated in accordance with methods compatible with the ODAN.

b.

A summary of the results of the land use census required in Specification 4.21.F.2.

1 This tabulation supplements the requirements of $20.2206 of 10CFR Part 20.

l Amendment Es. 27,S9,100,l':9,172,174

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