ML20086P152

Amends 156 & 145 to Licenses DPR-77 & DPR-79,respectively, Changing Title of Person on Operations Dept Staff Holding Senior Operation License from Operations Manager to Operations Superintendent

ML20086P152
Person / Time
Site:	Sequoyah
Issue date:	12/16/1991
From:	Hebdon F Office of Nuclear Reactor Regulation
To:
Shared Package
ML20086P154	List: ML20086P152 ML20086P155
References
NUDOCS 9112260225
Download: ML20086P152 (9)

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.. NUCLEAR REGULATORY COMMISSION '

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-TENNESSEE VALLEY AUTHORITY-DOCKET-NO. 50-327-'

SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE ki.F Amendment No.156 -

License No. DPR-77--

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1The Nuclear Regulatory Comission (the Comission) has found that::

A.

.The application for_ amendment by Tennessee Valley Authority (the licensee)datedDecember 14, 1990 and supplemented October 15, 1991, complies with the standards and requirements of the Atomic Energy Act of L1954, as amended;(the Act),-and the Comission's rules and

regulations, set forth inL10 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 Comission;;

C.

- There.is reesonable assurance'(1) that the activities authorized by :

thisiamendment '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;

'DJ The.fssuance of this amendment will not be inimical to the comon

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 Cossiission's regulations and all applicable requirements have been: satisfied.

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LAccordingly, the license is amended by changes to the Technical Specifications as-indicated in the' attachment to' this-license amendrent

and paragraph 2.C.(2) of Facility Operating License No. DPR-77'is hereby amended to read as follows:-

(2). Technical Specifications:

The Technical Specifications contained in Appendices A and B, as revised through Amendment No.156, are hereby ~ incorporated in 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, with implementation within 30 days.

FOR.THE NUCLEAR REGULATORY COMMISSION

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L Frederick J. HeNon, Director-Project Directorate 11-4 Division'of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes.to the Technical Specifications Date of Issuance: De: ember 16, 1991 d

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ATTACHMENT TO LICENSE AMENDMENT N0.156-FACILITY OPERATING LICENSE NO. DPR-77

.n DOCKET NO. 50-327 t

f Revise the-Appendix A Technical Specifications by removing the pages:

identiried below and inserting the enclosed pages.. The revised pages-are: identified by the captioned amendment number.and contain marginal, lines indicating:_the area of change.

REMOVE

' JNSERT

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ADMINISTRATIVE CONTROLS c.

-A. Radiological; Control; technician #shsll.beonsitewhenfuelisinthe reactor.

d.

'All' CORE ALTERATIONS-shall be observed and directly supervised by

--either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities-during this operation.

A Fire Brigade'of at least 5 members shall be~ maintained onsite:at.

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all, times.

1The Fire Brigade shall not include the Shift Supervisor and 2 other members of-the minimum _ shift crew necessary for safe-shutdown of the unit or-any personnel required for other essential functions.during a-fire emergency, f.

The Operations Superintendent shall holdLa Senior Reactor Operator _ license. l g.

Administrati_ve procedures shall be developed and implemented to 3

limit the working hours of unit staff who. perform safety-related functions (i;e.,-senior reactor operators, reactor operators, assistant unit operators,. Radiological Control, and key maintenance

. personnel).-

l Adequate shift coverage.shall be maintained without routine heavy-use of overtime._ Tho objective shall be to have operating personnel work:a normal 8-hour day, 40-hour week while the unit is operating.

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However. in_the event that unforseen problems require substantial

. amounts'of: overtime to-be used, or during extended periods of shutdown;for refueling, major maintanance, or major plant modification, on a-temporary basis the following guidelines shall be followed:

1.

'An: individual should not be permitted to work more than 16

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hours straight,_ excluding shift turnover time.

- 2.

An individual should not be-permitted to work more than 16

. hours in~any 24-hour: period, nor more-than 24-hours-in any

.48-hour period,-nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, all

_-excluding shift turnover time.

3.

A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work periods, including shift turnover ~ time.

4.

Except during extended shutdowr periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guideli'es shall be authorized by the Plant

-Manager (or Duty Plant Manager), or

- gher levels of management,.in accordance with established procedu.e3 and with documentation of the basis for granting the deviation.

Controls shall be included in the procedures such that-individual overtime shall-be reviewed monthly by the Plant-Manager or his designee to assure that excessive hours __have not been assigned.

Routine deviation from the above guidelines is not authorized.

1. The Radiological Control technician and fire brigade composition may be less i

than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence provided immediate action is taken to fill the required positions.

-SEQUOYAH - UNIT 1 6-2 Amendment No.

156, 58, 74, 152 32 W

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ADMINISTRATIVE CONTROLS MONTHLY REACTOR OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or Safety Valves shall s

be submitted on a monthly basis no later than the 15th of each month following the calendar month covered by the report.

CORE OPERATING LIMITS REPORT 6.9.1.14 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:

1.

Moderator Temperature Coefficient BOL and EOL limits and 300 ppm surveillance limit for Specification 3/4.1.1.3, 2.

Shutdown Bank Insertion Limit for Specification 3/4.1.3.5, 3.

Control Bank Insertion Limits for Specification 3/4.1.3.6, 4.

Axial Flux Difference Limits for Specification 3/4.2.1, 5.

Heat Flux Hot Channel Factor, K(z), :nd W(z) for Specification 3/4.2.2, and 6.

Nuclear Enthalpy Hot Channel Factor and Power Factor Multiplier for Specification 3/4.2.3.

6.9.1.14.a The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by NRC in:

1.

WCAP-9272-P-A, " WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY". July 1985 (W Proprietary).

(Methodology for SpeciTications 3.1.1,3 - Moderator Temperature 4

Coefficient, 3.1.3.5 - Shutdown Bank Insertion Limit, 3.1.3.6 -

Control Bank Insertion Limits, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Chanr71 Factar, and 3.2.3 - Nuclear Enthalpy Hot Channel Factor.)

2.

WCAP-10216-P-A, " RELAXATION OF CONSTANT AXIAL OFFSET CONTROL Fq SURVEILLANCE TECHNICAL SPECIFICATION", JUNE 1983 (W Proprietary).

(Methodology for Specification 3.2.1 - Axial Fliix Difference (Relaxed Axial Offset Control) and 3.2.2 - Heat Flux Hot Channel Factor (W(z) surveillance requirements for F Methodology).)

q 3.

WCAP-10266-P-A Rev. 2, "THE 1981 REVISION OF WESTINGHOUSE EVALUATION MODEL USING BASH CODE", March 1987, (W Proprietary).

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor).

4 SEQUOYAH - UNIT 1 6-21 Amendment Nos. 52, 58, 72, 74, 117, 152, 155, 156

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j WASHINGTON, D. C. 2055G TENNESSEE VALLEY AUTHORITY-DOCKET NO. 50-328 SE000YAH NUCLEAR PLANT, UNIT-2 A__ENDMENT TO FACILITY OPERATING LICENSE M

Amendment No.145 License No. DPR-79 1.

' The Nuclear Regulatory Comission (the Comission) has. found that:-

A.

The application for amendment by Tennessee Valley Authority-(the licensee) dated December _14, 1990 and supplemented October 15, 1991,.

complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's ru?es and regulations set forth in 10=CFR Chapter I;

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B..

The facility will operate in conformity with the application, the provisions of the'Act, and +he rules and regulations of the Comission; C.

lThere'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 amendrent will not be inimical to the comon

~ defense and security c. to the health and safety of the public;'and E.

The issuance of this amendrent is in accordance with 10 CFR Part 51 of the Comunission's regulations and_ all applicable requirements have been satisfied.

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- 2.

Accordingly, the license is amended by changes to the Technical

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Specifications as indicated in-the attachment to this Itcense amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-79 is hereby-amended to read as-follows:

(2). Technical Specifications The' Technical: Specifications contained in Appendices A and B, as revised through Ament' ment No '145, are hereby incorporated in the license.- The licenste shall operate the facility in accordance with theLTechnical Specifications.

3.

This license amendment is effective as~of'its date of11ssuance, with implementation within 30' days.

FOR THE HUCLEAR REGULATORY COMMISSION rN I

Frederick J. Hebdon, Director

~ Project Directorate:II-4 Division of Reactor Projects - I/II-Office of Nuclear Reactor Regulation Attachuent:

Changes ~to the Technical

Specifications

- Date of Issuance: January 16, 1991 a'

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[g-ATTACHMENT T0 LICENSE AMENDMENT N0t.145 FACILITY OPERATING LICENSE NO. OPR-79

-DOCKET NO. 50-328

. Revise the Appendix A Technical Specifications by renoving the pages

. identified below and inserting.the enclosed'pages. The revised pages are identified by the captioned amendment number and-contain marginal lines; indicating the area of' change.

REMOVE INSERT 6-2 6-2 4

4 ADMINISTRATIVE CONTROLS-c.

A Radiological Cor.crol technician # shall be onsite when fuel is in the reactor.

I d.

All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities

'during this operation.

AFireBrfgadeofatleast5membersshallbemaintainedonsiteat e.

all times.

The Fire Brigade shall not include the Shift Supervisor and the 2 other members of the minimum shift crew necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency.

f.

The Operations Superintendent shall hold a Senior Reactor Operator license.

g.

Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety related functions (i.e., senior reactor operators, reactor operators, assistant unit operators, Radiological Control, and key maintenance personnel).

Adequate shift coverage shall be maintained without routine he'vy use of overtime.

The objective shall be to have operating personnel work a normal 8-hour day, 40-hour week while the unit is operating.

However, in the event that unforseen problems require substantial amounts of overtime to be used, cr during extended periods of shutdown for refueling, major maintanance, or major plant modification, on a temporary basis the following guidelines shall be followed:

1.

An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.

2.

An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, all excluding shift turnover time.

3.

A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work periods, including shift turnover time.

4.

Except during extended shutdown period-the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized by the Plant Manager (or Duty Plant Manager), or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.

Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Plant Manager or his designee to assure that excessive hours have not been assigned.

Routine deviation from the above guidelines is not authorized.

1. The Radiological Control technician and fire brigade composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in l

order to accommodate unexpected absence provided immediate action is taken to fill the required positions.

SEQUOYAH - UNIT 2 6-2 Amendment No. 50, 66, 142 145

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