ML19312C436

Amends 54,54 & 51 to Licenses DPR-38,DPR-47 & DPR-55, Respectively,Revising Tech Specs to Identify or Conservatively Account for Radionuclides at Low Activity Levels in Gamma Emitters

ML19312C436
Person / Time
Site:	Oconee
Issue date:	11/23/1977
From:	Schwencer A Office of Nuclear Reactor Regulation
To:
Shared Package
ML19312C433	List: ML19312C432 ML19312C436
References
NUDOCS 7912130959
Download: ML19312C436 (10)

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UNITE D STA TES e

NUCLEAR REGULATORY COMMisslON p

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t CASHINGTON, D. C. 20555

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V DUKE POWER C0fiPANY DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT NO. 1 AMENDfiENT TO FACILITY OPERATING LICENSE Amendment No. 54 License No. DPR-38 1.

The U. S. Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Duke Pome Company (the licensee) dated May 6,1977, 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 publ.ic, and (ii) that such activities will be conductedincomfliancewiththeCommission'sregulations; 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 issuar.ce of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all appl'icable requirements have been satisfied.

2.

Accordingly, the license is aniended by ghanges to the Techn.ica1 Specifications a's indicated in the-attachment to this licehse amendment and paragraph 3.8 of Facility License No. CPR-38 is hereby amended to read as follows:

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"(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 54, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications."

3.

This license amendment is effective within 30 days of issuance.

FOR THE NUC' EAR REGULATORY COMMISSION

[ht&d'$V A. Schwencer, Chief Operating Reactors Branch #1

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Division of Operating Reactors

Attachment:

Changes to the Technical Specifications Date of Issuance:

November 23, 1977 i

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UNITE D ST ATES y*)kg,.,i NUCLEAR REGULATORY COMfAlsSION y,

WASHINGTON. D. C. 205b5

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DUKE POWER COMPANY DOCKET N0. 50-270 OCONEE NUCLEAR STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 54 License No. DPR-47 1.

The U. S. Nuclear Regulatory Commission (the Commission) has found tha t:

A.

The application for amendment by Duke Power Company (the licensee) dated May 6,1977, 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 Commissio,n; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety cf 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 issuanc.e of this amendment is in accordance <ith 10 CFR Part 51 of the Commission's regulations and all tpplicable require-ments have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this licen,e amendment and paragraph 3.lt of f acility Liu nse No. DPR-47 is hereby amended to read as follows:

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"(2) Technical Specifications -

The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 54, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications."

3.

This license amendment is effective within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION httvert%u l.

A. Sthwencer, Chief Operating Reactors Branch el Division of Operating Reactors

Attachment:

Changes to the Technical Specifications Date of Issuance: November 23, 1977 1

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION g

g WASHINGTON D. C.20555 e....,P DUKE POWER C0tiPANY DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT NO. 3 AliENDitENT TO FACILITY OPERATING LICENSE Amendment N0.51 License No. DPR-55 1.

The U.S. Nuclear Regulatory Commission (the Ccmmission) has found that:

A.

The application for amendment by Duke Power Company (the licensee) dated May 6,1977, 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 applicaton, 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 healtn and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of *.his 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.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attac.hment to this license amendment and paragraph 3.B of Facility License No. OPR-55 is hereby amended to read as follows:

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"(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.51

, are hereby incorporated in the license. The licensae shall operate the facility in accordance with the Technical Specifications."

3.

This license amendment is effective within 30 days of issuance.

FOR TiiE NUCLEAR REGULATORY COMMISSION

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'l 6(VilhD A. schwencer, Chief

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Operating Reactors Branch #1 Division of Operating Reactors

Attachment:

Changes.to the Technical Specifications l

Date of Issuance:

November 23, 1977 O

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ATTACHMENT TO LICENSE AMEN 0 MENT NOS. 54, 54 AND 51 FACILITY OPERATING LICENSE NOS. OPR-39, DPR-47 AND OPR-55 DOCKET NOS. 50-269, 50-270 AND 50-287_

Revise Appendix A as follows: Remove the following pages and replace with identically numbered revised pages.

Remove Replace 4.1-11 4.1-11 4.1-12 4.1-12 4.1-13 4.1-13 e

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s TABLE 4.1-3 Cont.

111NIMUM S A M P 1. I N G FREQUENCY eo f

Sensitivity Limits of Item Check Frequency Lab Analysis for Waste Principal Gamma Emitters (5)

a. Prior to release

a. Gamma Nuclides <5x10 pCi/ml l

7. Low Activity Waste a.

Tank, Condensate including Dissolved of each batch Dissolved Cases <10 pC1/ml ui Test Tank, Noble Cases C'

Condensate Monitoring Tank,

b. Radiochemical Analysis

b. Monthly

b. (10-pCi/ml Laundry-Ilot Sr 89,90

.c. Tritium

c. Monthly c.

<10 pCi/ml

d. Gross Alpha Activity

d. Monthly

d. <10-pCi/ml Principal Camna Emitters (5)

a. Prior to release a.

<10-pCUcc (gases) l

8. Vaste Gas Decay a.

-O Tank of each batch (10 pCi/cc (particulates 1

and lodines)

b. Tritium

b. Prior to release

b. <10 pCL/cc of each batch Iodine Spectrum (

a. Weekly a.

<10 ci/cc

-10

9. Unit Vent Sampling a.

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b. Particulates 0

1) Principal Gamma Emitters (5)

1) Weekly Composite

1) <10 gijcc l

-II

2) Cross Alpha Activity

2) Quarterly on a

2) <10 pCL/cc sample of one week duration

-I

3) Radiochemical Analysis

3) Quarterly Composite

3) (10 pCi/cc j

Sr 89,90

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TABI.E 4.1-3 Cont.

MINIMUM SAMPLING F1FQUENCY

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Sensitivity Limits of 6

Item Check Frequency Lab Analysis for Waste S

~ pCi/cc

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c. Gases by Principal Gamma

c. Weekly

c. <10

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P Emitters (5)

10. Keowee liydro Dam Measure Leakage Flow Rate Annually Dilution Flow (n

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11. Condenser Air Ejector Measure Iodine Partition One time if and when primary u3

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Partition Factor Factor in Condenser to secondary leaks develop "3

12. Reactor Building

a. Principal Gamma Emitters (5)

a. Each Purge

a. <10 pci/cc (gases) l

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<10 pCi/cc (particulates and iodines) c

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.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 pCi/ml and will be redetermined for each 10 pC1/ml increase in gross beta-gamma activity analysis thereafter. A radiochemical analysis for this purpose shall coasist of a quantitative measurement of 95 percent of the radionuclides 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 dissolved gaseous activities, rodlochemical analysis for Sr-89 and Sr-90, and tritium analysis.

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il TABLE 4.1-3 Continued Bm 5

MINIMUM SAMPLING FREOUENCY

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(3) When gross activity increases by a factor of two above background, an iodine analysis will be made and performed thereafter when the gross beta-gamma activity increases by 10 percent.

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(4) When the activity level exceeds 10 percent of the limits of Specification 3.9, the sampling frequency S2 shall be increased to a minimum of once each day.

This can be done by RLA-44 (Unit Vent Iodine Monitor).

When the gross activity release rate exceeds one percent of the maximum release rate and the average on gross activity release rate increased by 50 percent over the previous day, an analysis shall be performed for iodines and particulates. This can be done by RIA-44 (Unit Vent Iodine Monitor) and RIA-43 (Unit Vent Particulate Monitor).

(5) For certain mixtures 'of gamma emitters, it may not be possible to measure the activity level of some radionuclides in the mixture to their specified sensitivity limit when other nuclides are present in v.

the sample at much higher activity levels. When this situation exists, the minimum detectable activities L

(MDA) of the nuclides not meet ing the sensit ivity limits will be compared with the total activity present 1

from ot,her nuclides.

If the MDA of each of these nuclides is less than 1% of the total activity present, it will not he included in the total activity determination.

If it is greater than 1% of the total activity, it will be added to the total activity at its MDA concentration.

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