ML20030E142

Amends 9 & 1 to Licenses DPR-77 & DPR-79,respectively, Extending Date by Which Ceiling Tiles in Control Room Must Be Replaced & Authorizing Replacement of Flow Rate Monitors No Later than Next Refueling

ML20030E142
Person / Time
Site:	Sequoyah
Issue date:	09/08/1981
From:	Adensam E Office of Nuclear Reactor Regulation
To:
Shared Package
ML20030E143	List: ML20030E142 ML20030E148 ML20030E152
References
NUDOCS 8109180043
Download: ML20030E142 (10)

Text

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TEkHESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH HUCLEAR PLANT, UNIT 1 AMENDl1ENT TO FACILITY OPERATING LICENSE Amendment No. 9 License No. DPR-77 1.

The Nuclear Regulatory Comnission (the Commission) having found that:

A.

The applications for anendment to the Sequoyah Nuclear Plant, Unit 1 (the facilityi Facility Operating License No. DPR-77 filed by the Tennessee Valley Authority (licensee 1, dated August 14. August 20 and August 25, 1981, comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Conais-sion's regulations as set forth in 10 CFR Chapter I; B.

The facility will eperate in conformity with the license, as amended,

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the provisions of the Act, and the rules and regulations of the Com-mission; C.

There is reasonable assurance (i) tht? the activities authorizer by this anendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in coapliance with the Connission's regulations; D.

The issuance of this amendment will not be inimical to the connon defense and security or to the health and safety of the public; and E.

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

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. ccordingly, the license is hereby anended as follows:

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A.

Add paragraph 2.C.(16)(c) to read:

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(c) By Septenber 30, 1981, TVA shall rcplace the control room YLg ceiling panels with par 15 acceptable to NRC.

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The Appendix A Technical Specific;tions are changed as indicated in Toa the attachnent to this license anensoent and paragraph 2.C.(2) o' Facility Operating License No. UPR-7/ is hereby anended to read as

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2-(2) Tecnnical Specifications The Technical Specifications contained in Appendix A, as revised through Amendent No. 9, are hereby incorporated into the licea%.

1 The licensee shall operate the facility in accordance with the Technical Specifications.

.i. This license amendrant is effective as of its date of issuance.

70R THE NUCLEAR REGULATORY C0HMISS10N Elinor G. Adensam Acting Chief Licensing Branch No. 4 Division of Licensing

Attachment:

Appendix A Technical Specification Changes Ddte of Issuance: Septenber 8, 1981

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ATTACtHENT TO LICENSE AMENDHENT NO. 9 FACILITY OPERATING LICENSE NG, 9PR-77 DOCKET NO. 50-327 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding over-leaf pages are also provided to maintain document coimleteness.

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T_ABLE 3.3-13 (Continued)

TADLE NOTATION At all times.

During waste gas disposal system operation.

• • • During shield building exhaust system operation.

With the nur.her of channels OPERABLE less than required by the ACTION 40 Minimum Channels OPERABLE requirement, the contents of tne tank (s) may be released to the environment for up to 14 days provided that prior to initiating the release:

a.

At least two independent samples of the tahk's contents are analyzed, and b.

At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineup; Otherwise, suspend release of radioactive effluents via this pathway.

With the number of channels CPERABLE less than required by the ACTION 41 Minimum Channels GPERABLE requirement, efflu.ej1t releases via this pathway may continue for up to 30 days v provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

With the number of channels OPERABLE less than required by the-ACTION 42 Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and these savles are analyzed for noble gas gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

With the number of channels OPERABLE less than required by the ACTIDH 43 Minimum Channels GPERABLE requirement, operation of this waste gas disposal system may continue for up to 7 days provided grab samples are collected at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. With the hydrogen and oxygen monitors inoperable, be in at least HOT 51ANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

With the number of channels OPERABLE less than required by the ACTION 44 Minirma Channels OPERABLE requirement, effluent releases via the affected pathway may continue for-up to 30 days provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after the channel has been declared inoperable samples are continuously collected with auxiliary sanpling equipment as required in Table 4.11-2.

Until the replacement of the applicable flow rate monitors, but in no case later than before startuo followina the hrst refueling outace. this 30-day time limit is wai ved for effit.ent -eleases via the shield building

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SECONDARY CONTAINMEllT BYPASS LEAKAGE PATHS 2 0:

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RELEASE LOCATION PENETRATION X-85A Excess Letdown Heat Eschanger Auxiliary Area X-84A Pressurizer Relief Tank Gas Sample Auxiliary Area

.ii X-90 Control Air Auxiliary Area

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X-93 Accumulator Sample Auxiliary Area X-94ABC Radiation Sample Auxiliary Area O :. -

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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH HUCLEAR PLANT, UNIT 2 AMENDMENT 10 FACILITY OPERATING LICENSE Amendment No.1 Licanse No. DPR-79 1.

The Nuclear Regulatory Comission (the Comission) having found that:

A.

The applications for amendment to the Sequoyah Nuclear Plant, Unit 2 (the facility) Facility Operating License Ho. DPR-79 filed by the Tennessee Valley Authority (licensee), dated August 14, August 20, and August 25, 1981, comply with the standards and requirements of-the Ato:aic Energy Act of 1954, as anended (the Act) and the Comis-sion's regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the license, as amended, the provisions of the Act, and the rules and regulations of the Com-mission; 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 regulations; D.

The issuance of this anendment 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 CFP, Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is hereby amended as follows:

A.

Change paragraph 2.C.(6)(c) to read:

(c) TVA shall replace the control room ceiling panels with panels acceptable to HPC by September 30, 1981.

B.

The Appendix A Technical Spec'.ficat' ions are changed as indicated in the attachnent to this 1. cense amendment and paragraph 2.C.(2) of Facility Operating Lit. case No. DPR-79 is hereby amended to read as fn11 me.

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.. (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.1, are hereby incorporated into the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMISSION I

Elinor G. Adensam, Acting Chief Licensing Branch No. 4 Division of Licensing

Attachment:

Appendix A Technical Specification Changes Date of Issuance: September 8, 1981

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ATTACIU4ENT TO LICEIAE AMENDl4ENT NO.1 FACILITY OPERATING LICENSE N% DPR-79 DOCKET NO. 50-328 Replace the following paces of the Appendix "A" Technical Specifications with the enclosed pages. Tht revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding over-leaf pages are also provided to maintain docuirent completeness.

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TABLE 3.3-13 (Continued)

TABLE NOTATION At all times.

During waste gas disposal systen operation.

• • • During shield building exhmist system operation.

ACTION 40 Witn the number of channels OPERABLE less than required by the Mininum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment for up to 14 days provided that prior to initiating the release:

a.

At least two independent samples of the tank's contents are analyzed, and b.

At least two technically qualified menters of the Facility Staff independently verify the release rate calculations and discharge valve lineup; Otherwise, suspend release of radioactive effluents via this pathway.

ACTI0il 41 With the number of channels OPERABLE less than required oy the Mininum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days 1/ provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

ACTION 42 With the number of channel; OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and these samples are analyzed for noble gas gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 43 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, operation of this waste gas disposal system may continue for up to 7 days provided grab samples are collected at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. With the hydrogen and oxygen monitors inoperable, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

With the number of channels OPERABLE less than required by the ACTION 44 Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 30 days provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> af ter the channel has been declared inoperable samples are continuously collected with auxiliary sampling equipnent as required in Table 4.11-2.

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MJntil the replacement of the applicable flow rate monitors but in no case later Llan oerore stsrtup roisowi ng t.ne first refueling outage, this omer>.30nday.. time. Limit..is..waf.vad..f.or...cf.f.lueat. releases-v ta-the-shiel(.bui4 ding --

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i i i PENETRATION RELEASE LOCATION X-84A Pressurizer Relief Tank Gas Sample Auxiliary Area iii X-85A Excess Letdown Heat Exchanger Auxiliary Area iii X-90 Control Air Auxiliary Area iii X-93 Acctmulator Sample Auxiliary Area iii X-94ABC Radiation Sample Auxiliary Area iii X-95ABC Radiation Sanple Auxiliary Area iii O

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