ML19308A886

Amend 36 to License DPR-38 Incorporating Tech Spec Changes. Proposed Tech Specs Encl

ML19308A886
Person / Time
Site:	Oconee
Issue date:	01/27/1977
From:	Schwencer A Office of Nuclear Reactor Regulation
To:
Shared Package
ML19308A883	List: ML19308A882 ML19308A886 ML19308A894
References
NUDOCS 7912120670
Download: ML19308A886 (7)

Text

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UNITE 3 STATES

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NUCLEAR RESULATORY COMMISSION j

j WASHINGTON, D. C. 20556 e

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DUKE POWER COMPANY DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT NO. 1

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AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 36 License No. DPR-38 1.

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

A.

The application for amendment by Duke Power Company (the licensee) dated May 27, 1976, 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 E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

5932120 D

2.

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

3.

This !icense amendment is effective as of 'the dat.e of its issuance.

FOR THE NUCLEAR REGULATORY C0f! MISSION It?&WW A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors

Attachment:

l Changes to the Technical Specifications Date of Issuance:

January 27, 1977 0

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ATTACHENT TO LICENSE AENDENTS AENDENT NO. 36 TO DPR-38 AENDENT NO. 36 TO DPR-47 AE NDMENT NO. 33 TO DPR-55 DOCKETS NOS. 50-269, 50-270 AND 50-287 Revise Appendix A as follows:

Remove pages 4.1-11, 4.1-12, 4.11-4 and 4.11-5 and insert identically numbered pages.

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TABLE 4.1-3 Cont.

8 MINIMUM SAMPLING F R E Q_U E N C Y_

Sensitivity of Waste Analysis in Lab Frequency Check Item

a. Gamma Nuclides <5x10" uCi/ml

7. Low Activity Waste

a. Gamma Isotopic Analysis

a. Prior to release of each batch Dissolved Cases <10 uCi/ml Tank, Condensate including Dissolved Test Tank, Nohle Cases

-8 Condensate

b. <10 uCi/ml Monitoring Tank,

b. Radiochemical Analysis

b. Monthly Laundry-Hot Sr 89,90

c. <10 uCi/ml

c. Monthly

c. Tritium

d. <10' pCi/ml

d. Monthly

d. Gross Alpha Activity

a. Prior to release a.

<10 uic (gases)

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a. Gamma Isotopic Analysis

, 8. Waste Gas Decay of each batch

<10 uCi/cc (particulates and fodines)

Tank

+

4

b. Prior to release

b. <10 uCi/cc

b. Tritium of each batch

-0

a. <10 uCi/cc

)

a. Weekly

9. Unit Vent Sampling

a. Iodine Spectrum

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b. Particulates

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1) Gamma Isotopic Analysis

1) Weekly Composite

1) <10 aci/cc

2) <10" uCi/cc 3

2) Quarterly on a

2) Gross Alpha Activity sample of one week duration

-11 g

3) Radiochemical Analysis

3) Quarterly u mposite

3) <10 aci/cc g

Sr 89,90 M

ba

TABLE 4.1-3 Cont.

MINIMUM SAMPL1NG FREQUENCY Sensitivity of Waste Item Check Frequency Analysis in Lab

c. Cases by Gamma Isotopic

c. Weekly

c. <10~

pCi/cc Analysis

10. Keowee Hydro Dam Measure Leakage Flow Rate Annually Dilution Flow

11. Condenser Air Ejector Measure Iodine Partition One time if and when primary Partition Factor Factor in Condenser to secondary leaks develop 410[f0uci/cc (gases)

12. Reactor Building

a. Camma Isotopic Analysis

a. Each Purge a.

<10 pCi/cc (particulates and iodines) c

-6

b. Tritium

b. Each Purge

b. <10 pCi/cc (1) When radioactivity level is greater than 10 percent of the limits of Specification 3.1.4, the sampling frequency shall be increased to a minimum of once each day.

(2)

E determination will be started when gross beta-gamma activity analysis indicates greater than 10 uCi/ml and will be redetermined for each 10 pCi/ml increase in gross beta-gamma activity analysis thereafter.

A radiochemical analysis for this purpose shall consist of a quantitative measurement of 95 percent of the radionuulides in the reactor coolant with half lives greater than 30 minutes.

This is expected to consist of gamma isotopic analysis of the primary coolant, including ofssolved gaseous activities, radiochemical analysis for Sr-89 and Sr-90, and tritium analysis.

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TABLE 4.11-2 OFFSITE RADIOLOGICAL MONITORING PROGRAM Analysis Type Samples Schedule Gross Alpha Gross Beta Gamma Analysis Specific Nuclides 131

1. Water Supply (raw)

Monthly x

x x

I 89 90 3

Quarterly x

x x

Sr.

Sr.

H

2. Water (3)(other than Monthly x

x x

}( }

89Sr, 90Sr, 3H raw water supply)

Quarterly x

x x

131

3. Airborne Particulates Weekly I

89Sr, 90 (including iodine)

Monthly x

x x

Sr

4. Rain and Settled Dust Monthly x

x Quarterly x

5. Radiation Dose and Quarterly l

Dose Rate (mR, mR/hr)

I

6. Lake Bottom and Semiannually x

Co, Sr, Sr Shoreline Sediment (as available) including benthos

7. Aquatic Vegetation Semiannually h

Cs, K.

Sr, Sr 1

and/or Plankton (as available)

8. Terrestrial Vegetation-Quarterly x

Cs, K,

I pasture grass, forage, (as available) and consnercial crops f9 31

9. Milk Weekly I

)

Sr, 90Sr, Cs,

'.0K, 137 c.

Monthly

, Quarterly x

g 3H

10. Fish Semiannually (

'Sr, Sr, Cs, Kl x

[

11. Soil Triennially x

'Sr, ' Sr NOTES: (1) Water supply samples will be composited weekly for monthly analyses.

(2) Record status of waste discharge operations at time of sampling for surface water samples.

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(3) Surface water samples are to be collected closely following liquid discharge to allow for sufficient time for movement downstream in order to verify diultion, or monthly for continuous discharge.

i (4) When animals are on pasture.

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g (5) Milk samples will be composited weekly for monthly analysis.

(6) When fish samples are available.

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TABLE 4.11-3 ANALYTICAL SENSITIVITIES The sensitivity of the analyses for various radionuclides in representative samples is typically as follows:

Airborne Particulate Water or Gag Fish Milk Vegetation Soil Analysis (pCi/1)

(pCi/m )

(pCi/kg, wet)

(pCi/1)

(pCi/kg,vetl (pCi/kg, dry) gross beta 1

1 x 10-gross alpha 0.5 1 x 10-3H 330 330 K

1200 200 400 Mn 15 130 Fe 30 260 Co 15 130 65Zn 30 260

'Sr e

10 5 x 1J 40 10 40 600

' Sr 2

1 x 10-8 2

8 150 Zr-Nb 10 I

1.5 7 x 10-0.5 8dII 134, 137

-2 Cs 15 1 x 10 130 15 100 150 CI) 140 m

Ba-La 15 O'

15 a

N E

The sensitivity of the radiation exposure measurements (gross gamma) is approximately 10mR for a three-month

$ integrated exposure and.005mR/hr for exposure rate measurement.

$ (1)

These sensitivities may vary depending on the water content of the vegetation samples.

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