ML18031B081

Proposed Suppl 3 to Tech Spec 201,revising Shift Crew & Reporting Requirements

ML18031B081
Person / Time
Site:	Browns Ferry
Issue date:	12/10/1986
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18031B080	List: ML18031B079 ML18031B081
References
TAC-56027, TAC-56028, TAC-56029, NUDOCS 8612160270
Download: ML18031B081 (20)

Text

ENCLOSURE 1 PROPOSED CHANGES BROWNS FERRY NUCLEAR PLANT (BFN)

TS 201i SUPPLEMENT 3 shi2i60270 85000259 PDR ADOCN 0 PDR P

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Table 6.2.A Hinimum Shift Crew Re uirementsb Position Units in 0 eration T e of License 0 2d 3 Senior Operatora 1 1 1 1 SRO Senior Operator 0 1 2 2 SRO Licensed Operators 3 3 3 3 RO or SRO 4S Additional Licensed Operatorsc 0 1 2 2 RO or SRO Assistant Unit Operators (AUO) 4 4 5 -

5 None Shift Technical Advisor (STA) 0 1 1 1 None Health Physics Technician 1 1 1 1 None Note for Table 6.2.A

a. A senior operator will be assigned responsibility for overall plant operation at all times there is fuel in any unit,

b. Except for the senior operator discussed in note "a", the shift crew composition may be one less than the minimum requirements of Table 6.2.A for a period of time not to exceed two hours in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2.A. This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.

c~ One of the Additional Licensed Operators must be assigned to each control room with an operating unit.

The number of required licensed personnel, when the operating units are controlled from a common control room, are two senior operators and four operators.

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6.3 PLANT STAFF VALIFICATIONS Qualifications of the Browns Ferry Nuclear Plant management and operating staff shall meet the minimum acceptable levels as described in ANSI-N18.1, Selection and Training of Nuclear Power Plant Personnel, dated March 8, 1971. The qualifications of the Health Physics Supervisor will meet or exceed the minimum acceptable levels as described in Regulatory Guide 1.8, Revision 1, dated September 1975. The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design and transient and accident response and analysis.

6.4 TRAINING I

A retraining and replacement training program for station personnel shall be in accordance with ANSI N18.1, Selection and Training of Nuclear Power Plant Personnel, dated March 8, 1971. The minimum frequency of the retraining program shall be every two years.

6.5 PLANT REVIEW AND AUDIT 6.5.1 Plant 0 erations Review Committee (PORC) 6.5.1.1 Function

a. The PORC shall function to advise the Plant Manager in all matters related to nuclear safety.

b. This advisory function shall be performed by, the PORC acting in a formal meeting or by members acting individually without a formal meeting.

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6.5.1.4 For expedited meetings, when it is not practical to convene 'as a-group, the chairman or alternate chairman may conduct committee business by polling the members individually (by telephone or in person) or via "a serialized review.

VORVM

~y 6.5.1.5 The quorum necessary for the PORC to act in a formal meeting shall consist of the chairman or alternate chairman and at least five members or their alternates. Members shall be considered present if they are in telephone communication with the committee.

RESPONSIBILITIES 6.5.1.6 The PORC shall be responsible for the activities listed below.

The PORC may delegate the performance of reviews, but will maintain cognizance over and responsibility for them, e.g.,

subcommittees.

a. Review of administrative procedures for the control of the technical and cross-disciplinary review of (1) all procedures required by specification 6.8.1.1, and changes thereto, (2) any other procedures and changes thereto .

determined by the Plant Manager to affect nuclear safety.

b. Review of the administrative procedures required by specification 6.8.l.l.a. and changes thereto.

c. Review of emergency operating procedures and changes thereto.

d. Review implementing procedures of the Radiological Emergency Plan and the Industrial Security Program.

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shall be secured by lock(s). The key(s) shall be'nder the .

administrative control of the shift engineer. In the case of a high radiation area established for a period of 30 days or less, direct surveillance to prevent unauthorized entry may be substituted for permanent access control.

Health Physics personnel, or personnel escorted by Health Physics lg personnel, in accordance with approved emergency procedures, shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.

6.9 REPORTING RE UIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the Director of the Regional Office of NRC, unless otherwise noted.

6.9.1.1 STARTUP REPORT

a. A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic 6-20

on pocket dosimeter, TLD, or film badge measurements. Small exposures totaling less than 207. of the individual total ~

dose need not be accounted for. In the aggregate, at least

,r 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

b. Any-mainsteam relief valve that opens in response to reaching its setpoint or due to operator action to control N

reactor pressure shall be reported.

"-A single submittal may be made for a multiple unit station.

~=This tabulation supplements the requirements of 20.407 of 10 CFR Part 20.

6.9.1.3 MONTHLY OPERATING REPORT Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Office of Inspection and Enforcement, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Office, to be submitted no later than the fifteenth of each month following the calendar month covered by the report. A narrative summary of operating experience shall be submitted in the above schedule.

6.9.1.4 REPORTABLE 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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I, 6.9.1.'5 RADIOACTIVE EFFLUENT RELEASE REPORT%

A 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 Enforcemenmt- 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 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 Materials in Liquid and Gaseous Effluents from Light-Water-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 the meteorological conditions concurrent with the release of gaseous effluents during each quarter as outlined in Regulatory Guide 1.21, Revision 1, with data summarized on a quarterly basis following the-format of Appendix B thereof. Calculated offsite dose to humans resulting from the release of effluents and their subsequent dispersion in in the atmosphere shall be reported as recommended in Regulatory Guide 1.21, Revision l.

~A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.

6.9.1.6 SOURCE TESTS Results of required leak tests performed on sources if the tests reveal the presence of 0.005 microcurie or more of removable contamination.

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BOARD OF DIRECTORS GENERAL MANAGER MANAGER OF aO DEPUTY MANAGER N

I NUCLEAR SAFETY REVIEW BOARD NUCLEAR DIRECTOR DIRECTOR DIRECTOR DIRECTOR DIRECTOR DIRECTOR SITE DIRECTORS OP OF OF OP OP OP NUCLEAR NUCLEAR NUCLEAR NUCLEAR NUCLEAR SAFETY

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AND NUCLEAR NUCLEAR ROJECT MANAGERS CO&NSTRUCTION QA EhGINEERING SERVICES TRAINING & LICENSING Figurc 6.2-1 Offsite Organization for Facility Management and Technical Support

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I DIRECTOR DIRECTOR DIRECTOR DIRECTOR DIVISION OF OF NUCLEAR SITE DIVISION OF DIVISION OF NUCLEAR QA ENGINEERING DIRECTOR NUCLEAR NUCLEAR SAFETY CONSTRUCTION AND LICENSING SITE SITE SITE QA PROJECT PLANT SERVICES ODIFlCATION ENGINEER MANAGER MANAGER SAFETY AND MANAGER MANAGER LICENSING MANAGER ASSISTAN PLANT MANAGER INDUSTRIAL SAFETY>>

UNIT RADIOLOGICAL TECHNICAL UP ER INTEND ENTS MAINTENANCE CONTROL SUPERINTENDENT SERVICES (3) SUPERINTENDENT OPERATIOI'IS UNIT SUPERVISORS AINTENANCE (3) UPERVISORS HEMISTRY ENGINEERING 3)

SHIFT SHIFT CREWS TECHNICAL (3). ADVISOR SHIFT ENGINEER (SRO) ~ RESPONSIBIIJlY FOR FIRE PROTECTION PROGRAM ASSISTANT SHIFT ENGINEER SRO SENIOR REACTOR OPERATOR UCENSE UNIT OPERATOR (RO) (SRO) RO REACTOR OPERATOR IJCENSE ASSISTANT UNIT OPERATOR AUXILIARYUNIT OPERATOR FIGURE 6.2-2 FACILITY ORGANIZATION

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Enclosure 2 Description and Justification TVA BFNP 201 Supplement 3 Descri tion of Additional Chan es Table 6.2.A, Minimum Shift Crew Requirements, page 6-3, is revised to delete note "e" which described shift technical advisor qualifications. The same words were added to section 6.3, Plant Staff Qualifications, page 6-4, and therefore no change to the current technical specification requirements or-those of theproposed amendment is made.

Plant Operations Review Committee (PORC) responsibility item 6.5.1.6.d is revised to include review of implementing procedures of the Industrial Security Program. This change will return this item to its current TS wording.

Pages 6-20, 6-22, .and 6-23 of the proposed amendment simply "had notes moved from the bottom of the page to the end of the section to which the notes apply.

The Offsite Organization, Figure 6.2-1 of TS 201 Supplement 2, is revised to include the Director of Nuclear Construction and to delete site organizations now shown on figure 6.2-2.

N The Facility Organization, Figure 6.2-2, of TS 201 Supplement 2, is revised to include the Site Safety and Licensing Manager, Project Engineer, Assistant Plant Manager, Plant Operations Review Staff, Industrial Safety, Shift Technical Advisor, and notes for licensed positions and fire protection responsibility.

Revised Justification for Chan e TVA is a corporate agency of the Federal Government whose major policies, programs, and organizations are determined by a full-time, three member Board of Directors. Members of the, Board are appointed by the President and confirmed by the Senate for nine-year terms. The staff of Browns Ferry Nuclear Plant within the Office of Nuclear Power is responsible for operating and maintaining TVA's Browns Ferry Nuclear Plant. The changes contained in this amendment request deal specifically and solely with the administrative controls required by TS.

Changing the Administrative Controls section to standard format with the standard page numbering system, deleting unnecessary notes, deleting references to previously deleted requirements, adopting STS terminologyf adding new minimum shift crew requirements, and updating the description of the TVA organization are all within the guidance provided by NRC in STS and will result in increased clarity and usefulness and therefore, increased safety.

The changes to the description of PORC and the technical review process are consistent with the regulatory position of Regulatory Guide 1.33, revision 2, February 1978. The requested amendment requires that decisions affecting

Revised Justification for Chan e (Continued) safety be made at the proper level of responsibility with the necessary technical advice and review. The Plant Manager retains overall responsibility for the execution of the administrative controls necessary to assure plant safety. However, the detailed technical reviews can be accomplished by qualified individuals not encumbered with other managerial duties, but possessing the technical expertise to provide a thorough review. The current TS requirement for review of changes is actually satisfied by individuals of a similar responsibility level; however, considerable management time is consumed in the assigning of these personnel to review each item, collecting results from..those reviews, and finally attending a formal meeting to recommend a disposition. The method requested by this amendment eliminates much of the unnecessary effort and at the same time provides for a more consistent and timely review and approval process. It= will focus responsibility and accountability to the technical reviewers and provide a better review. Cross-disciplinary review will also be improved from current methods since reviewers will be able to concentrate on their particular areas of expertise.

The most important safety consideration is that this amendment permits PORC members to focus their attention on the safety significance of the issues essential to the safe operation of the plant thereby improving PORC's effectiveness. This aspect is increasingly important because of the growing number of procedures, procedural changes, and modifications that must be reviewed.

For the reasons stated above, TVA has concluded that these proposed TS changes will significantly enhance nuclear safety.

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