ML18026A792

Proposed Tech Spec Re Administrative Controls

ML18026A792
Person / Time
Site:	Browns Ferry
Issue date:	11/28/1983
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18026A791	List: ML18026A790 ML18026A792
References
TVA-BFNF-TS-194, NUDOCS 8312050560
Download: ML18026A792 (18)

Text

ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION REVISIONS BROWNS FERRY NUCLEAR PLANT UNITS 1,.2, AND 3 (TVA BFNP TS 194) 83ii28 83i2050560 05000259 PDR ADOCK P PDR

PROPOSED CHANGES UNIT 1

6.0 The events listed below sly be reported within 30 days to the USMC,. Docurrent Control Desk, Washington D. C., with a cogy to the Regional Administrator of the appropriate Regional Office.

The written report shall include, as a minimun, a completed copy of a licensee event report form.

Information provided on the licensee event regort form shall be supplerrented, as needed, by additional narrative material to provide the information required by 10 CFR 50.73.

a. (1) The completion of any reactor shutdown required by the technical specifications.

(2) Any operation or condition prohibited by the technical specif ications.

(3) Any, deviation from the technical specifications authorized pursuant to 10 CER 50.54(x) .

b. Any event or condition that resulted. in the plant, including its principal safety barriers, being seriously degraded, or that resulted in the plant being:

(1) In an unanalyzed'condition that significantly compromised plant safety.,

(2) In a condition that was outside the design basis of the ply.

(3) In a condition not covered by the plant, operating and emergency procedures.

c. Any natural phenom non or other- external condition

, that posed an actual threat to the safety of the plant or significantly hungered site personnel in the performance of duties necessary for the safe,,

operation of the plant.

d. Any event or condition that resulted in manual or automatic actuation of any Engineered ~~ety Feature (ESF),, including the Reactor Protection (RPS) . However, actuation. of an ESF, including the RPS, that resulted from and was gart of the preplanned sequenc'e during testing or reactor operation need not be reported.

e. Any event or condition that alone could have prevented the fulfillment of the safety function of structures or systems that are needed to:

352

6.0 (1) Shutdown the reactor and shutdown condition.

raintain it in a safe (2) Remove residual heat.

(3) Control the release of radioactive material.

(4) Nitigate the consequences of an accident.

Events covered in this paragraph may include one or rare procedural errors, equipment failures, and/or discovery of design, analysis, fabrication, constructions and/or procedural inadequacies. However, individual component failures need not be reported pursuant to this paragraph if redundant equipment in the same system was operable and available to perform the required safety function.

Any event where a single cause or condition caused at least one independent train or channel to become inoperable in multiple systems or two independent trains or channels to become inoperable in a single system designed to:

(1) Shutdown the reactor and maintain't in a safe shutdown condition.

(2) Remove residual heat.

(3) Control the releases of radioactive naterial.

(4) Mitigate the consequences of an accident.

(1) Any airborne radioactivity release that exceeded t~n times the applicable concentrations of the loots specified in Appendix B, Table II of 10 CFR 20 in unrestricted areas, when averaged over a time period of one hour.

(2) Any liquid effluent release that exceeded two tim s the limiting combined Maximum Permissible Concentration (MPC) (See Note 1 of Pppendix B to 10 CER 20) at the point of entry into the receiving water (i.e., unrestricted area) for all radionuclides except tritium and dissolved noble gases, when averaged over a tine period of one hour.

353

6,.0 KYZE: These reports also meet the effluent release reporting requirements of 10 CFR 20.405 (a)

(5).'ny

h. event that posed an actual threat to the safety of the plant or significantly hampered site personnel in the performance of duties necessary for the safe operation of the plant including fires, toxic gas releases, or radioactive releases.

354

6.0 ADNENTSTRATXVE CONTROLS

3. Uni ue Re artin Re uirements Radioactive Ef fluen Release Re rt.

A rcport: on the radioactive di ch~rqeu relea ed fzom the site durinq t.he previous 6 months of operation shall be submitted to the Director of..the Regional, Office of Xnspection and Enforcement within 60 days after January 1 and July 1 of'ach year. The'eport sha'll include a summary of the quantitias of radioactive liquid and gaseous effluents released and "olid waste shipped from the plant as delineated in Regulatory Guide'.21, Revision 1, ".'leasuring, Evaluating, a'nd Reporting Radioactivity in Solid Wastes and Releases of Radioactive Haterials in Liquid and Gaseaus Effluents from Light-Water>>Cooled Nuclear Power Plants,". with data summarixeo on a quarterly basis followinq the format of Appendix 0 thereof.

The report shall, include a summary of the meteorological candit'lans concurrent with the release o'f gaseous effluents during each quarter as outlined in Requlatory Guide 1.21, Revision 1, with data summariced on a quarterly basis following the format of Apoendix B thereof .. Calculated af f site do e to humans resulting frart the release of effluent" an6 their subsequent dispersian in the atmosphere shall be reported a" recommended in Requlatory Guide

'I

l. 21, Revision l.

355

PROPOSED CHANGES UNIT 2 I

6.0 The events listed below shall be reported within 30 days to the USMC, Document Control Desk, Washington D. C., with a copy to the Regional Administrator of the appropriate- Regional Office.

The written report shall include, as a minimum, a completed copy of a licensee event report form.

Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide the information required by 10 ~ 50.73.

(1) The completion of any reactor shutdown required by the technical specifications.

t (2) Any operation or condition prohibited by the technical specif ications.,

(3) Any deviation from the technical specifications authorized pursuant to 10 CFR 50.54(x) .

b. Any event or condition that resulted in the plant, including its principal safe+ barriers, being seriously degraded, or that resulted in the plant being:

(1) In an unanalyzed condition"that significantly compromised plant saiety.

(2) In a condition that was outside the design basis of the plant.

(3) In a condition not covered by the plant'.

operating and emergency procedures.

co Any natural phenorrmon or other external condition that posed- an actual threat to the safety of the plant or'ignificantly hampered site personnel in the performance of duties necessary for the safe operation of the plant.

d., Any event or condition that resulted in manual or automatic actuation of any Engineered Safety

'Feature . (ESF), including the Reactor Protection (RPS). However, actuation. of an ESF, including the RPS, that resulted fr'om and was part, of the preplanned sequence during testing or reactor operation need not be reported.

e. Any event or condition that alone could have prevented the fu1fillmnt of the safety function of structures or systems that are needed to:

352

6.0 (1) Shutdown the reactor and maintain shutdown condition.

it in a safe (2) Remove residual heat.

(3) Control the release of radioactive material.

(4) Mitigate the consequences of an accident.

K7I'r: Events covered in this paragraph may include one or more procedural errors, equipment failures, and/or discovery of design, analysis, fabrication, construction, and/or procedural inadequacies. However, individual component failures need not be reported pursuant to this paragraph if redundant equi~>>,'t in the same system was operable and available to perform the required safety function.

Any event where a single cause or condition caused at least one independent tr'ain or channel to become inop rable in multiple systems or two independent trains or" channels to become'- inoperable in a single system designed to:

(1) Shutdown the reactor and maintain it in a safe shutdown condition.

(2), Remove residual heat.

(3) Control the releases of radioactive material.

(4) 'Mitigate the co~~ quences of an accident.

go (1) Any airborne radioactivity release that exceeded two times the applicable concentrations of the limxts specified in Appendi.". 8, Table II of 10 CFR 20 in unrestricted areas, when averaged over a tiae period of one hour.

(2) Any liqu'd eff~mt release that a~ceded two

~ti"a comb~M~LWM~m.

to the

'0".L 10 CER 20)

~) jSBB 1 Qf. ~~

W~~-~~e at the point of entry into the receiving water (i.e., unrestricted area) for all radionuclides except tritium and dissolved noble gases, when averaged over a time period of one hour.

353

6.0 LATE: These reports also meet the effluent

~

release reporting requirements of 10 20.405 (a)

(5).'ny event that posed en actual threat to the safety of the plant or significantly hampered site personnel in the performance of duties necessary for the safe operation of the plant including fires, toxic gas releases, or radioactive releases.

354

6.0 ADMlNISTRATXVE CONTROLS Uni ue Reoortin Re uirements Radioactive Ef fluent Release Re rt A report on the radioackive dischurqc" released f rom the site during the previous 6 month" of operation shall be submitted to the Oirector of the Regional Of fice of Lnspection'nd Enforcement within 60 days after January 1 and July 1 of each year. The report shall include a summary of the quantities of radioactive, liquid and gaseous effluents released and solid ~aste shipped from the plant as delineated in Regulatory Gu'j,de 1.21, Revision 1, uHeasuring, Evaluating, 'a'nd Reporting Radioactivity in Solid Wastes and Releases of Radioactive Haterials in Liquid and Gaseous Effluents from Light-water-Cool>d Nuclear Power Plants,'! with data summarize'd on a quarterly basis followinq the format of Appendix B thereof.

The report shall .include a summary of the meteorological condit'ions concurrent with the release of gaseous effluents during each quarter as outlined in Regulatory Guide 21, Revision 1, with 1

data summari"ed on a quarterly basis following the format of hpoendix B thereof.. Calculated offsite dose to humans resulting frori the release of e f fluent.", an 9 their subsequent di" i per pe sion in the atmosphere shall be reported as, recommended in Regula tory Gui de 1. 2 1, Revis ion 1.

355

PROPOSED CHANGES UNET 3

6.0 The events listed below shall be reported within 30 days to the USNRC, Docunent Control Desk, Washington D. C., with a copy to the Regional Administrator of the appropriate Regional Office.

The written report shall include, as a minimum, a completed copy of a licensee event report form.

Information provided on the license'e event report form shall be supplemented, as needed, by additional narrative material to provide the information required by 10 CFR 50.73.

'a ~ (1) The completion of any reactor shutdown required by the technical specifications.

(2) Any operation or condition prohibited by the technical specif ications.

(3) Any deviation from the technical specifications authorized pursuant to 10 CFR 50.54(x) .

b. Any event or condition that resulted in the plant, including its principal safety barriers, being seriously degraded, or that resulted in the plant being:

(1) In an unanalyzed condition that significantly compromised plant safety.

(2) In a condition~at was outside the design basis of the plant.

(3) In a condition not covered by the plant operating and emergency procedures.

c, Any natural phenomenon or other external condition that posed an actual threat to the safety of the plant or significantly hampered site personnel in the performance of duties necessary'or the safe operation of the plant.

d. Any event or condition tnat resulted in nanual cr automatic "ctuation of any Engineered Safety Feature (ESF), including the Reactor Protection (RPS). Havever, actuation. of an ESF, including the BPS, that resulted from and was part of the preplanned sequence during testing or re=ctor o~ration need not be reported.

e. Any event or condition that alone could have prevented the fulfil1ment of the safety function of structures or systems that are needed to:

382

6.0 (1) Shutdown the reactor and maintain shutdum condition.

it in a safe (2) Remove residual heat.

(3) Control the release of radioactive material.

(4) Mitigate the consequences of an accident.

K7ZE: Events covered in this paragraph nay include one or more procedural errors, equipnent failures, and/or discovery of design, analysis, fabrication, construction, and/or procedural inadequacies. However, individual component failures need not be reported pursuant to this paragraph if redundant equiprrent in the same system was operable and available to perform the required safety function.

Any event where a single cause or condition caused at least one independent train or channel to become inoperable in multiple systems or two independent trains or channels to become inoperable in a single system designed to:

(1) Shutdown the reactor and maintain shutdown condition.

it in a safe (2) Remove residual heat.

(3) Control the releases of radioact've material.

(4) Mitigate the consequences of an accident.

g, (1) Any airborne radioactivity release that exceeded tvo tines the applicable concentrations of the limits specified in Appendix B, Table II of 10 CFR 20 in unrestricted areas, when averaged over a tim period of one hour.

(2) Any liquid effluent release that exceeded two times the limiting combined Maximum Permissible Concentration (MPC) (See Note 1 of Appendix B to 10 CFR 20) at the point of entry into the receiving water (i.e., unrestricted area) for all radionuclides except 'tritium and dissolved noble gases, when averaged over a tine period of one hour.

383

6.0 NOTTE

These reports also meet the effluent release reporting requiranents of 10 CFR 20.405 (a) (5).

h. Any event that posed an actual threat to the safety of the plant o- significantly lampered site personnel in the performance of duties necessary for the safe operation of the plant including fires, toxic gas releases, or radioactive releases.

384

6.0 ADHINISTRATIVE CONTROLS

3. Uni ue Re ortin Re uirements Radioactive Ef fluent Relea -e Re rt A rcport on the radioaot ive di schargc" released f:om the site during the previous 6 months of operation shall be submitted to the. Director of the .

Regio'na1 Of fice 'of Inspection and, Enforcement wi:thin 60 days after January 1 and July of each 1

year. The repoit shall include a summary of the g>>antities of radioactive liquid and gaseous effluent'eleased and solid waste shipped from the plant as delineated in Regulatory Guide 1.21, Revision 1, "Neasuring, Evaluating,'nd Reportirig Radioactivity in Solid wastes and Releases of Radioactive Haterials in Liquid and Gaseous

'Effluent" from Light-Water-Cooled Nuclear Power Plants,'! with data summarized on a quarter'ly basis following he format of Appendix 0 thereof.

The report shall .include a summary of the

~

meteorological condir'.ious concurrent 'with the release of gaseou" eff luents during each quarter as outlined in Regulatory Guide 1.21, Revision l, with data summarited on a quarterly basis following the format of Apaendix 9 thereof .. Calculated of f site do" e to humans resulting frora the release of ef f luents an i thei r subsequent dispersion in the atmosphere shall be reported a" recommenrled in Reg>>latory Guide 1. 21, Revision 385