ML20137Y624
| ML20137Y624 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 11/22/1985 |
| From: | Thompson H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20137Y628 | List: |
| References | |
| TAC-53503, NUDOCS 8512110089 | |
| Download: ML20137Y624 (9) | |
Text
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UNITED STATES
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g NUCLEAR REGULATORY COMMISSION r,
wasmworos, o. c. nosss g.....,f DUKE POWER COMPANY DOCKET NO. 50-369 McGUIRE NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 49 License No. NPF-9 1.
The Nuclear Regulatory Comission (the Commission or the NRC) has found that:
A.
The app!' cations for amendment-to the McGuire Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-9 filed by the Duke Power Company (the licensee) dated January 12, 1984, and January 17, 1985, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application as amended, the provisions of the Act, and the regulations of the Comission; C.
There is reasonable assurance: (1) 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 Comission's regulatiers set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the comon defense and security or the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, Facility Operating License No. NPF-9 is changed as follows:
A.
Change paragraph 2.C.(11)f.(3) to read:
(3) The licensee shall upgrade the in-containment portion of the incore thennocouple system prior to startup following the first refueling outage, and shall provide a schedule for ypgrade of the remainder of the system in the Regulatory Guide 1.97 Accident Monitoring Review Report submittal pursuant to NUREG 0737 Supplement 1,.
1 8512110009 051122 PDR ADOCK 05000369 P
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The license is further amended by page changes to the Technical Specifica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-9 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 49, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
4.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATO'4Y COMISSION
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.. Thompson, r,
frector Di ion of Lice i Of ce of Nuclear R actor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
November 22, 1985
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UNITED STATES g
NUCLEAR, REGULATORY COMMISSION 7.
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- t DUKE POWER COMPANY DOCKET NO. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 30 License No. NPF-17 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-17 filed by the Duke PowerCompany(thelicensee)datedJanuary 17, 1985, complies with the standards and requiremer.ts of the Atomic Energy Act of 1954, as amended (the Act), and the Consission's regulations set forth in 10 CFR Chapter I;
B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance: (1) 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 set forth in 10 CFR Chapter I; D.
Theissuanceofthislicenseamendmentwillnotbeinimicaltothe common defense and security or to the health and safety of the public; 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 hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 30. are hereby incorporated into this licenss.
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.2-The licensee shall operate the facility in accordance with the Tech-nical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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A
- 4R.Elinor G.
densam, Chief I
Licensing Branch No. 4 Division of Licensing
Attachment:
Technical Specification Changes Date of Issuance: November 22, 1985 a
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I ATTACHMENT TO LICENSE AMENDMENT NO. 49 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET N0. 50-369 AND TO LICENSE AMENDMENT N0. 30 FACILITY OPERATING LICENSE NO. NPF-17 D0CKET NO. 50-370 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical lins indicating the area of change. The corresponding over-leaf pages are also prcvided to maintain document completeness.
Amended Overleaf fag ga,g 3/4 11-6 3/4 11-5 3/4 11-15 3/4 11-16 i
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RADI0 ACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUB (IC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS (see Figure 5.1-4) shall be Ilmited:
a.
During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and b.
During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
APPLICABILITY: At all times.
ACTION:
a.
With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above Ilmits, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. This Special Report shall also include:
(1) the results of radiological analyses of the drinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act.*
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions from Itquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the 00CM at least once per 31 days.
o AThese requirements are app 1tcable only if the drinking water supply is taken from the river 3 miles downstream of the plant discharge.
t McGUIRE - UNITS 1 and 2 3/4 11-5
RA010 ACTIVE EFFLUENTS LIQUID RA0 WASTE TREATNENT SYSTEN LINITING CONDITION FOR OPERATION 3.11.1.3 The Liquid Radwaste Treatment System shall be OPERA 8LE and appropriate portions of the system shall be used to reduce releases of radio-activity when the projected doses due to the liquid effluent, from each unit, l
to UNRESTRICTED AREAS (see Figure 5.1-4) would exceed 0.06 area to the total body or 0.2 mrom to any organ in a 31-day period.
I APPLICABILITY: At all times.
ACTION:
With radioactive liquid waste being discharged without treatment and a.
in excess of the above Ilmits and any portion of the Liquid Radweste Treatment System not in operation, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report that includes the following information:
1.
Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or i
subsystems, and the reason for the inoperability, 1
2.
Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.
Summary description of action (s) taken to prevent a recurrence, b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIRENENTS 4.11.1.3.1 Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the 00CM when water systems are being released without being processed by its Radweste Treatment System.
4.11.1.3.2 The installed Liquid Radweste Treatment System shall be demon-strated OPERA 8LE by meeting Specifications 3.11.1.1.and 3.11.1.2.
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MCOUIRE - UNITS 1 and 2 3/4 11-6 Amendment No.49 (Unit 1)
Amendment No. 30 (Unit 2)
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l RADI0 ACTIVE EFFLUENTS GASE0US RA0 WASTE TREATMENT SYSTEM i
LIMITING CONDITION FOR OPERATION 3.11.2.4 The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to to gaseous effluent releases, from each unit, to areas at and beyond the SITE SOUNDARY (see Figure 5.1-3) would exceed:
a.
0.2 mrad to air from gamma radiation, or b.
0.4 mrad to air from beta radiation, or c.
0.3 mrom to any organ of a MEM8ER 0F THE PUBLIC.
APPLICA8ILITY: At all times.
ACTION:
I a.
With radioactive gaseoud waste being discharged without treatment and in excess of the above limits, in lieu of a Licensee Event j
Report, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that includes the following information:
1.
Identification of any inoperable equipment or subsystems, and the reason for the inoperability, 2.
Actions (s) taken to restore the inoperable equipment to 0PERABLE status, and 3.
Summary description of actions (s) taken to prevent a recurrence.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
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$URVEILLANCE REQUIREMENTS i
4.11.2.4.1 Doses due to gaseous releases from each unit to areas at and beyond the SITE SOUNDARY shall be projected at least once per 31 days in accordancewiththemethodologyandparametersinthe90CMwhengaseous streamsarebeingreleasedwithoutbeingprocessedbyitsReevasteTreat- ?
ment System.
4.11.2.4.2 The installed Gaseous Radweste Treatment ystem shall be demon-strated OPERABLE by meeting Specifications 3.11.2.1 and 3.11.2.2 or 3.11.2.3.
MCGUIRE - UNITS 1 and 2 3/4 11-15 Amendment No. 49 (Unit 1)
Amendment No. 30 (Unit 2)
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RADI0 ACTIVE EFFLUENTS
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EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the WASTE GAS HOLDUP SYSTEM shall be limited to less than or equal to 2% by volume whenever the hydrogen concentra-tion exceeds 4% by volume.
APPLICABILITY: At all times.
ACTION:
With the concentration of oxygen in the WASTE GAS HOLOUP SYSTEM a.
greater than 2% by volume but less than or equal 4% by volume, reduce the oxygen concentration to the above Ilmits within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, b.
With the concentration of oxygen in the WASTE GAS HOLOUP SYSTEM greater than 4% by volume and the hydrogen concentration greater than 4% by volume, immediately suspend all additions of waste gases to the system and reduce the concentration 6f oxygen to less than or equal to 4% by volume, and immediately take ACTION a. above, The provisions of Spcifications 3.0.3 and 3.0.4 are not applicable.
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c.
SURVEILLANCE REQUIREMENTS 4.11.2.5 The conceatrations of hydrogen and oxygen in the WASTE GAS HOLOUP SYSTEM shall be determined to be within the above limits by monitoring the waste gases in the WASTE GAS HOLDUP SYSTEM with the hydrogen and oxygen monitors required OPERA 8LE by Table 3.3-13 of Specification 3.3.3.9.
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McCUIRE - UNITS 1 and 2 3/4 11-16
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