ML18026A922

Proposed Tech Specs,Incorporating 10CFR50.73 Reporting Requirements.Info Deleted.Nshc Determination Encl

ML18026A922
Person / Time
Site:	Browns Ferry
Issue date:	03/22/1984
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18026A921	List: ML18026A920 ML18026A922
References
NUDOCS 8404020034
Download: ML18026A922 (51)

Text

ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION REVISIONS BROMNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 (TVA BFNP TS 194 SUPPLEMENT 1) 8404020034 840322 PDR ADOCK 05000259 P PDR

P l ~

PROPOSED CHANGES UNIT 1

I i s +wbg. b 3

'A n

la0 DEFZNXTIONS (Cont'd) vr b ev

10. ~I.o ic - A logic is an arrangement of relays, contactsg and other components that produces a decision output., sl fel ~lnftlotln - A logic that receive signals free channels and produces decision outputs to the actuation logic.

(b) Actuation - A logic that receives signals (either from initiation logic or channels) and produces decision outputs to accomplish a protective action.

Functional Tests - A functional test is the manual operation or initiation of a system, subsystem, or components to verify that it functions within design tolerances (e.ge the manual start it of a core spray pump to verify that it g runs and that pumps the required volume of water) .

X. Shutdown - The reactor is in a shutdown condition when the reactor mode i switc h s in the shutdown mode position and no core alterations arc being performed.

En ineered Safe uard - An engineered safeguard is a safety system the'actions of which are essential to a safety action required in response to accidc:ts.

Z. Re or"able Event A rePortable event shall ba any of those conditions specified in section 50.73 to 10'PR Part 50.

6.0 ADMINISTRATIVE CONTROLS All reportable events.

h. All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety.

i. Reports and meeting minutes of the PORC:

8. AUDITS Audits of unit activities shall be performed u'nder the cognizance of the NSRB. These audits shall encompass.

a. The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months.

b. The performance, training and qualifications of the entire.

unit staff at least once per 12 months.

C ~ The results of actions taken to co'rrect.'deficiencies occurring in unit equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.

The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 monthsr.

I e. The Site Radiological Emergency Plan and implementing procedures at least once per 24 months.

r The Plant Physical Security Plan and implementing procedures at least once per 24 months.

g. Any other area of unit operation considered appropriate =

, by the NSRB or the Manager of Power.

h. The Facility Fire Protection Program and irhplementing procedures at least once per 24 months.

i. An independent fire protection and loss prevention program inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel or" an outside fire protection firm.

An inspection and audit of the fire protection and loss prevention program shall be performed by "an outside qualified fire consultant at intervals no greater than 3 years.

334

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~g 6~0 AOMINI! TRATIVF. CONTROLS r

I

'I'he f<)ll(: serves in an advisory capacity to the

~aslant superintendent and as an investigating and reporting body to the Nuclear Safety Review, Board in matters related to safety in plant operations.

The plant superintendent has the final responsibility in determining the matters that should be referred to the Nuclear Safety Review Board The responsibility of the committee will include:

Review all standard and erpergency operating and maintenance instructions and any proposed revisions thereto, with principal attention to provisions for safe operation.

b. Review proposed changes to the Technical Specifications.

Ca Review proposed changes to equipment or systems having safety significance, or which may constitute 'ian unreviewed safety question" pursuant to 10 CFR 50.59.

d. Investigate reported or suspected incidents involvinq safety questions, violations of the Technica3, Specifications, and violations of plant instructions pertinent to nuclear safety. I e ~ Review reportable event~~ unusual events,

! operating anomalies and abnormal perf ormance of plant equipment. j

f. Maintain a general surveillance of. plant

'activities to identif possible 'safety hazards.

ga Review plans for special fuel handling, plant maintenance, operations, and tests or experiements which may involve special safety considerations, and the results thereof, where applicable.

h- adequacy of quality assurance program I'eview and recommend any, appropriate'hanges.

la Review implementatinq procedures. of the Radiological Emergency plan and the Industrial Security program on an annual basis.

l 336

6.0 6.4 en e en P n A. Any reportable event shall be promptly rep'orted to the Manager, Nuclear Production "nd shall be promptly reviewed by PORC.

This committee shall prepare a separate repo'rt for each reportable event. This report shall include an evaluation cause of the event and recommendations for appropriate of'he action to prevent or reduce the probability of a repetition of the event.

B. Copies of all such reports shall be submitted to the Manager Nuclear Production and the Chairman of the NSRB for their review.

C. The plant superintendent, shall notify the NRC as specified in Section 50.73 to 10 CFR Part 50 of the circumstances of any reportable event.

6.5 ion o aken n the en a t t s E ceeded Zf a safety limit is exceeded, the reactor shall be shut down and reactor operation shall not be resumed until authorized by the NRC.

A prompt report shall be made to the Manager, Nucleax Production, and the Chairman of the NSRB. A complete analysis of the circumstances

.leading up to and resulting from the situation, together with recommendations to prevent a recurrence, shall be prepared by the PORC. This report shall be submitted to the Manager, Nuclear and the NSRB. Notification of such occurrences will be

'roduction made to the NRC by the plant superintendent within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

..6.6 on er n eco s Records and/or logs shall. be kept in a manner convenient for review as indicated below:

1. All normal plant operation including such items as power level, fuel exposure, and shutdowns.

2. Principal maintenance activities.

3. Reportable Events 346

,l

6 0 ADMINISTRATIVE CONTROLS (b). Annual 0 crating Re ort A tabulation on an annual basis of the number of station, utility and other personnel (includinq contractors) receiving exposures greater than 100 mren/yr and their associated man rem exposure according to work and job functions,'.g., reactor operations and surveillance, inservice inspection, routine special maintenance (describe 'aintenance, maintenance), waste proce sing, and refuelinq.

The dose* assignment to various duty functions may bc estimates Lased on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20K of the individua'otal dose need not be accounted, for. In th>> aggregate, at least SOT of the total whole body dose received from external sources shall be a igned to specific major work functions.

E operat'g statistics and shutdown experience shall be submitte'd on a monthly basis to the Office of Inspection and Enforcement, O.s.'Nuclear Regulatory Commission, Washinqton, ".C.,20555, with a copy to the appropriate Regional Of,ice, to be submitted no later than the'enth of each month ollowing the calendar month covered by the reoort. A narrative s[CKlary of operating experience stall bc .submitted in the ahove schedule.

2. 'epor table Events Reportable events, including corrective actions and measures to prevent reoccurrence, shall be reported to the NRC in accordance with

, Section 50.73 to 10 CFR 50.

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Uni ue Be ortin Be uirements Radioactive Effluent Release Re ort report on the radioactive discharges released from the site during the previous 6 months of

.operation shall be submitted to the Director of the Regional Office of Inspection and E'nfor'cement within 60 days after,. January 1 and July 1 of each year. The report sha13. include a summary of the quantities of radioacti "e 1"'quid and gaseous effluents released and solid waste shipped from the plant as delineated in Regulatory Guide 1.21, Revision 1, "Heasuring, Evaluating, and Reporting Radioactivity in Solid Mastes and Releases of" Radioactive Materials in Liquid and Gaseous Ef f luents f rom Light-Mater-Cooled Nuclear Power plants," with data summarized on a quarterly basis following the format of Appendix B thereof.

The report shall include a summary of conditions concurrent. with the the'eteorological release of gaseous efiluents during each quarter as outlined in Regulatory Guide 1.21, Revision 1 with ~

data summarized on a quarterly ba is following the format of Appendix 8 thereof. Calculated of f site dose to humans resulting from the release, of effluents an9 their subsequent aisp.rsion in the a tmospher e shall be reported as' ecommended in Regu3.atory Guide l. 21, Revision 355

PROPOSED CHANGES UNIT 2

f~

1.0 DEFINITIONS (Cont'd)

~

a

10. ~Lo ic A logic is an arrangement of relays, contacts, and other components that produces a decision output.

fa) Inf~tiatfn A logic that receive signals from channels and produces decision outputs to the actuation logic.

(b) Actuation A logic that receives signals (eiCher from initiation logic or channels) and produces decision outputs to accomplish a protective action.

Functional Tests A functional test is the manual operation of a system, subsystem, or components to verify that or.'nitiation it functions within design toleranccs (e.g., the manual start of a core spray pump to verify Chat it runs and that it pumps the required volume of water).

X. Shutdown - Thc reactor is in a shutdown condition when the reactor mode switch is in thc shutdown mode position and no altexations arc being performed. 'ore

~gn fnaere~dgafe uard - An engineered safeguard is a safety system the actions of which are essential to a safety ection required in response to accidents.

Z~ Re ortable Event A reportable event shall be any of those conditions specified in section 50.73 to 10 'CFR Part 50.

7

6.0 ADMINISTRATIVE CONTROLS All reportable events.

h. All recognized indications of an unanticipated deficiency aspect of design or operation of structures,

'n some systems, or components that could affect nuclear safety.

i. Reports and meeting minutes of the PORC.'.

AUOITS Audits of unit activities shall be performed under the cognizance of the NSRB. These audits shall encompass.

a. The conformance of unit operation to provisions contained within the Technics.'. Specifications and applicable license conditions at least once per 12 months.

b. Thc performance, training and qualifications of the entire..

unit staff at least once per 12 months.

C ~ The results of actions taken to co'rrect deficiencies occurring in unit equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.

d. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months.

e. The Site Radiological Emergency Plan and implementing procedures at least once per 24 months.

f. The Plant Physical Security Plan and implementing, procedures at least once pcr 24 months.

g. Any other area of unit operation considered appropriate'y the NSRB or the Manager of Power.

h. The Facility Fire Protection Program and implementing procedures at least once per 24 months.

i. An independent fire protection and loss prevention program inspection and audit shall bc performed annuallY utilizing either qualified offsite licensee personnel or an outside fire protection firm.'n inspection and audit of thc fire protection and lo<<

prevention program shall be performed by in outside .qualified fire consultant at intervals no greater than 3 years 334

/ 1

~

6.0 ADMINISTRATTVF; CONTROL.'i

~

ggt J,r .s gn~$ ReyL>gng jb j~~ < u

'I'h~ I<)RC si.rveu in an advisory capacity to the Implant superintendent and as an investigating and reportinq body to the Nuclear Safety Review Board in matters related to safety in plant operations.

The plant superintendent has the final responsibility in determining the matters Review be referred to the Nuclear Safety that'hould Board.

J responsibility of the committee will include:

I The a~ Review all standard and emergency operating and maintenance instructions and any proposed revisions thereto, with principal attention to provisions for safe operation.

b. Review prpppsed changes to the Technical Specifications.

ci Review proposed changes to equipment or systems having safety significance, or which may const;itute uan unreviewed safety question" pursuant to 10 CFR 50 59.

d. Investiqate reported or suspected incidents involvinq safety questions, violations of the Technicag Specifications, and violations of plant instructions pertinent to nuc'lear

,safety.

e. Review repprtable even<<, unusual events, operating anomalies and abnormal, pe'rf ormance of plant equipment. I

f. Maintain a qeneral surveillance of plant activities to identify possible 'safety hazards.

qo Review plans for special. fuel. handling, plant

.maintenance, operations, and tests or experiements which may involve special safety considerations, and the results thereof, where applicable.

h. Review adequacy 'of quality assurance program and recommend any appropriate changes.

1 ~ Review implementatinq procedures of the Radiological Emergency Plan and the Industrial Security Proqram on an annual basis.

.~ 336

6.O 6.4 en A. Any reportable event shall be promptly reported to the Manager, Nuclear Production and shall be promptly reviewed by PORC.

This committee shall prepare a separate report for each reportable event. This report shall include an evaluation of the cause of the event and recommendations for appropriate.

action to prevent or reduce the probability of a repetition of the event.

B. Copies of all such repor ts shall be submitted to the Manager Nuclear Production and the Chairman of the NSRB for their review.

C. The plant superintendent shall notify the NRC as specified in Section 50.73 to 10 CFR Part 50 of the circumstances of any reportable event.

6.5 Zf a safety limit is exceeded, the reactor shall be shut down and reactor operation shall not be resumed until authorized by the NRC.

A prompt report shall be made to the Manager, Nuclear Production, and

~ . the Chairman of the NSRB. A complete analysis of the circumstances leading up to and resulting from the situation, together with

.. recommendations to prevent a recurrence, shall be prepared by the.

PORC. This report shall be submitted to the Manager, Nuolear.

Production and the NSRB. Notification'of such occurrences will be made to the NRC by the plant superintendent within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

6;6 0 s A. Records and/or logs shall be kept in a manner convenient for review as indicated below

1. All normal plant oper ation including such items as power level, fuel exposure, and shutdowns..

2. Principal maintenance activities.

3. Reportable Events 346

6. 0 AONINISTRATIVE CONTROLS (b) . Annual 0 era ting .Re or t A tabulation on an annual ba is of the number of statior., utility and other personnel (includinq contractors) 'eceiving exposures greater than 100 mremlyr and their associated" ~

man rom exposure according to work and job functions,+ e.g., reactor operations and surveillance, in s er vice inspection, routine ma intenance, special maintenance (describe maintenance), waste proce sing, and refueling.

The dose ass'gnment to various duty functions may bc e timates ba.,ed on pocket closimet'er, TLO, or f ilm badge measurements. Small exposures totalling less than 20Ã of the individua'otal dose need not be accountea for. Xn the aggregate, at least 00$ of the total whole body oose received from external sources shall bc a igned to specific,m'ajor work functions.

operating sta txstics and shutdown experience sha11 be submitted on a monthly basis to the Office of Xnspection and Enforcement, O.s..'nuclear Regulatory Commission, Mashinqton, ".c.. 20555, wi-h a copy .to the appropriate Regional Of.ice, to be submitted. no later.

than the tenth of each mon:h ,allowing the calendar month covered bX'""- rcoor< A narrative ..r"..xiary'f opernting experience shall be submitted in the above, schedule.

2. Reportable Events Reportable events, including. corrective actions'and mcasur es to prevent reoccurrence, shall be, reported to the HRC in accordance with Section 50.73 to 10 CFR 50.

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'354

n Uni ue Re ortina Re uirements Radioactive Ef fluent Release Re~ort A report on the radioactive discharqr.". released from the site during the previous 6 months of operation shall be submitted to the Director of .he Regional Office of Xnspection and Enforce ment within 60 days after January 1 and July 1 of each year. The report shall include'a surunary of the quantities of radioactive liquid and gaseous effluents released and solid waste shipped. from the as delineated in Regulatory Guide 1.21, 'lant Revision 1, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of

'f Radioactive Materials in Liquid and Gaseous' fluents from Light-Water-Cooled t(uclear Po~er Plants," with data summarized on a quarterly basis .

followinq the format of Appendix 9 thereof.

h The report shall include a sugary of the meteorological conditions concurrent with the release of gaseous efiluents during each quarter as outlined in Regulatory Guide 1.21. Revision.l, with data summarized on a quarterly basis following the format of Appendix 8 thereof. Calculated offsite dose to humans resulting from ~De rel'ease of effluents an9 their subsequent disprrsion in 'the atmosphere shall be reported as recommended in Regulatory Guide 1. 21, Revision l.

355

PROPOSED CHANGES UNIT 3

a protective trip function., A trip system may require one or more instrument channel trip signals related to one or more plant parameters in order to initiate trip system action. Initiation of action may require the tripping of a .'rotective sinqle trip system or the conincident tripping of two trip systems.

7~ Protect ve A t - An action initiated by the a

protection system when a limit is reached. A-protective action can be at a channel or system level.

8. P"o ect ve unc o - A system protective action which results from the protective action of the .

channels monitoring a particular plant condition.

f 9.. 8 mulated Auto c A ut t on -'iaelated automatic acutation means applying a simulated signal to the sensor to actuate the circuit in question.

10. Lg~c - A logic is an arrangement of relays, contacts, and other components that produces a decision output.

from channels and produces decision outputs to the actuation logic.

(h) ~ctcat n - A lcglc that sacalvas signals (either from initiation logic or- channels) and produces decision outputs to accomplish a protective action operation or initiation of a system, subsystem, or component to verify that it functions within design tolerances ( e.g., the manual start of a core spray pump to verify that volume of water)c it runs and that it pumps the required Xs ghut~d wn - The reactor is in a shutdown condition when the reactor mode switch is in the'shutdown mode position and no core alterations are being performed.

Ya En nee Sae - An engineered safeguard is a safety system the actions of which'are essential to a safety action required in response to accidents.

a Za .Re ortable Event A reportable event shall be any of those conditions specified in section 50.73. to 10 CFR Part 50.

6.0 ADMINISTRATIVE CONTROLS All reportable events,

h. All recognized indicat'ions of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety.

i. Reports and meeting minutes of the PORC.

8. AUDITS Audits of unit activities shall be performed under the cognizance of the NSRB. These audits shall encompass.

a. The conformance of unit operation to provisions contained within the Technical 'Specifications and applicable license conditions at least once per 12 months.

b. The performance, training and qualifications of the entire unit staff at least once per 12 months.

c. The results of actions taken to correct deficiencies occurring in unit equipment, structures,, systems or method of operation that affect nuclear safety at least once per 6.months.

d. The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months.

e. The Site Radiological Emergency Plan and implementing procedures at least once per 24 months.

f. The Plant Physical Security Plan and implemen'ting procedures at least once per 24 months.

g. Any other area of unit operation considered.appropriate by the NSRB or the Manager of Power.

h. The Facility Fire Protection Program and implementing procedures at least once per 24 months.

An independent fire protection and loss prevention program inspection and audit shall be performed annual,ly utilizing either qualified offsite licensee personnel or an outside fire prote'ction firm.

An inspection and audit of the fire protection and program shall be performed by an outside qualified.

loss'revention fire consultant at intervals no greater than 3 years.

364

6~0 /DMINISTRATIVE CONTROLS I

QQ~.l"" '30~3 ~H~ypc~ngJ,//~&i o The l&ltC serves in an advisory capacity to the plant superintendent and as an investigating and reporting body to the Nuclear Safety Review Board )

in matters related to safety in plant operations. ~ I The plant superintendent has the final responsibility in determining the matters .that should be referred to the Nuclear Safety Review ~~

Board.

The responsibility of the committee will include:

a. Review all standard and emergency operating and maintenance instructions and any proposed revisionq thereto, with principal attention to provisions for safe operation.

b Review proposed changes to the Technical Specificjtions.

Ci Review proposed changes to equipment or systems having safety significance," or which may consgitute <<an unreviewed safety question<<<. pursuant to 10 CFR 50 59 ~

d. Investigate reported or suspected incidents involving safety questions, violations of the Technicag Specifications, and violations of plant inytructions pertinent to nuclear safety.

e. Review reportable events, unusual events, operating anomalies, ""~

and abnormal performanoe of plant equipment.

Maintain .a general surveillance of plant activitigs to identify possible safety hazards.

Review plans for special 'fuel handlinj, plant maintenance, operations, and tests or experiements which may involve special safety considerations ~

.'nd the results thereof, where applicable.

Review adequacy of quality assurance program and recopmend any appropriate changes.

Review implementating procedures of the Radiological Emergency Plan and the Industrial security Program on an annual basis.

'366

6.O 6.4 e ~

ken n.t e o a rt ent n P nt e ton A. Any reportable event shall be promptly reported to the Manager, Nuclear Production and shall be promptly reviewed by PORC.

This committee shall prepare a separate report for each reportable event. This report shall include'n evaluation of the cause of the event and.recommendations for appropriate action to prevent or reduce the probability of a repetition of the event.

B. Copies of .",3,1 such reports shall be submitted to. the Manager Nuolear Production and the Chairman of the NSRB for their review.

C. The 'plant superintendent shall notify the NRC as specified in Section 50.73 to 10 CFR Part 50 of the circumstances of any reportable event.

6.5 e a en e e s ee ed If a safety limit is exceeded, 'the reactor shall be shut down and reactor operation shall not be resumed until authorized by the NRC.

A prompt report shall be made to the Manager, Nuclear Production, and the Chairman of the NSRB.. A complete analysis of the circumstances leading up to and resulting from the situation, together with recommendations to prevent a recurrence, shall be prepared by the PORC. This report shall be submitted to the Manager, Nuclear Production and the NSRB. Notification of such occurrences will be, made to the NRC by the plant superintendent within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

/

~. 6".6 o er n e rd A. .Records and/or logs 'shall be kept in a manner convenient for as indicated below: 'eview

1. All normal plant operation including, such items as power level, fuel exposure, and shutdowns.

2. Principal maintenance activities.

'3. Reportable Events 376 4

6~ 0 ADMINISTRATXVE CONTROLS

b. Annual 0 erat" 'Report A tabulation on an annual basis of. the number o= station, utility and other personnel

{including contr actors) r eceiving exposures greater ';ban. 100 mx'emlyr and their associated man rem exposure according to work and job' functions,+ e,g., reactor operations and survei'ance, inservice inspection, routine maintenance, special maintenance {describe maintenance), waste processinq, and refuelinq.

>he dose assignment to various duty functio'ns may be estimates kased on pocket dosimeter, TLD, or film badge measurements. Small exposures tota'ing less than 20% of the individual,.total dose need not be accounted for. Xn the aggregate, at least,'0% of'he total wgole body dose received from external

'sources shall be assigned to speci.fic major work functions.

C~ Monthl 0 erati n Re~err. Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the 'Office of Xnspection and Enforcement, U.S. Nuclear Regulatory Commission, Mashington, o.c. 20555, with a copy to the appropriate Regional Office, to be submitted no later than the tenth of each month following the calendar '

month covered by the report. A narrative eumnary of operati experience shall be submitted in the above schedule.

2~ Reportable Events

,Reportable events, including corrective actions and measures to prevent reoccurrence, shall be reported to the NRC in accordance with Section 50e73 to 10 CPR 50.

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3 ~ Uni ue Reoortin Re uirements A~ Radioactive 2 fluent Release Re rt A report on the radioactive discharges released frcm the site during the previous 6 months of opera" ion shall be submitted to the, Director of the Regional Office of In pection and Enforcement wizhin 60 days after January 1 and July 1 of each year. The report snail include a summary of the quanti ies of radioactive liquid a'nd gaseous, effluents released and solid waste shipped from the

'plant as delineated in Regulatory Guide 1.21. ~

Revision 1, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Haterials in Liquid and Gaseous E" luents from Light-Mater-Cooled Nuclear Power Plants" with data summar'zed on a'uarterly basis followinq the format of Aopendix B thereof.

The report shall include a summary of the meteorological conditions concurrent with the release of gaseous.effluents during each quarter as outlined :n Regulatory Guide 1.21, Revision 1, with data summarized on a quarterly basis following the fermat of Append' B thereof. Calculated offsite dose to humans resulting from'the release of e fluents and their subsequent dispersion in'.the atmosphere shall be reported as recommended in Regu'atory Guide 1.21, Revision 1.

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ENCLOSURE 2 BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 NO SIGNIFICIANT HAZARDS CONSIDERATION DETERMINATION (TVA BFNP TS 194 SUPPLEMENT 1)

Descri tion This change will update the technical specification requirements for reporting LERs to be compatible with the new section (50.73) and 10 CFR 50 and corrects gob titles where appropriate. In section 6.4 and 6.5, .

the copy of the Manager of Power was deleted, making. this area compatible with BWR Standard Technical Specifications.

Basis for Pro osed No Si nificant Hazards Consideration Determination The Commission has provided guidance concerning the application of the standards in 10 CFR 50.92 by providing certain examples (48 FR 14870).

One of the examples of actions involving no significant hazards consideration relates to a change. to make a license conform to changes

, in the regulations where the license change relates in very minor changes to facility operations clearly in keeping with the regulations. The proposed amendment is encompassed by this example in that the revision is being made to incorporate the reporting requirements of 10 CFR 50.73 which became effective January 1, 1984. The proposed revision has no effect on either limiting condition of operations (LCOs) or surveillance

're'quirements but only changes the Licensee Event Report (LER) reporting requirements to reflect those adopted by NRC in 10 CFR 50.73. On this basis, TVA proposes to determine that the proposed amendment does not involve a sigpificant hazards consideration.

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