ML20202F652

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Proposed Tech Specs 15.6 & 15.7,reflecting Administrative Control Changes
ML20202F652
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 01/29/1999
From:
WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20202F650 List:
References
NUDOCS 9902040128
Download: ML20202F652 (14)
v • d • e


Text

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NPL 99-0057 i si Page 1 of 14 15.6 ADMINISTRATIVE CONTROLS 15.6.1 RESPONSIBILITY 15.6.1.1 The Plant Manager - Peir! Beech Wcler P!rt @ere!rMr refe~ed te r ee Mmege) shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during absences from the Point Beach Nuclear Plant area of greater than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> and where ready contact by telephone or other means is not assured.

15.6.1.2 The Duty Shift Superintendent (or during his absence from the control room, the Duty Operating Supervisor) shall be responsible for the Control Room Command function.

15.6.2 ORGANIZATION 15.6.2.1 Onsite and offsite organizations shall be established for plant operation and corporate management, respectively.

a.

Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the Point Beach Nuclear Plant Final Safety Analysis Report, or plant procedures.

b.

The Plant Manager shall be responsible for overall safe plant safe l operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

9902040128 990129 ADOCK05000266[I*

PDR P

t PDR Unit 1 - Amendment No.-128 15.6.1/2-1 Septe* A, ' "

Unit 2 - Amendment No.-132

NPL 99-0057 i

Page 2 of 14 15.6 ADMINISTRATIVE CONTROLS (Continued) l ii6.2 OROANIZATION (Continued) 15.6.2.1 (Continued) l The Chief Nuclear Officer shall be an officer of the Company and c.

shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staffin operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

d.

The individuals who carry out health physics and quality L

assurance functions may report to the appropriate onsite manager; i

however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

FACILITY STAFF 15.6.2.2 Facility stafling shall be subject to the following requirements:

Each on-duty shift shall normally be composed of at least the a.

minimum shift crew composition (fer d! eder except "ie 2 "i t defre'ed) as follows:**

1.

Shift Superintendent (SRO)* - one per shift 2.

Duty-Shift Technical Advisor - one per shift located on-site on ten minute call to the control room 3.

Operating Supervisor (SRO)* - one per shift 4.

Operator (RO)* - two-three per shift for one or two unit operation * *

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- 41see-two peisliift fer-swowith neither I

umTm operation ***

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Non-licensed Operator

+"ce per 6:9 fer ene "-!+

l cperet!^"one per shift for each unit l'

containing fuel and an additional one per l

l shift when either unit is in operation"*

  • 22 "": 2 * !^: *":^ ""' * ^^^:2 ""

E ne Duty Te+ :ce! ^3:!rer ir !eented er 9e er ter l

H uteed!te eecen+ze!-^^~

Unit 1 - Amendment No.122 15.6.2-2

^ ugurt 25, "

. Unit 2 - Amendment No.134 l

NPL 99-0057 Page 3 of 14 15.6 ADMINISTRATIVE CONTROLS (Continued) 15.6.2 ORGANIZATION (Continued)

FACILITY STAFF (Continued) 15.6.2.2 (Continued) b.

^+ 'eert ene 1:cected Op nter 42 ! M :- the cer+re! reer 1

" tee fue! it i e!Ser reerter. When there is fuel in either unit, an SRO* shall be in the control room at all times. In i

addition to this SRO*, for each unit containing fuel, an RO*

or SRO* shall be present at the controls at all times.

DELETED A+ 'eert !"ze "c-red Op nterr &M! M precee+

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in te ecee! reer. d"-ing re cter r+Mup, rc%du'ed re-ter 4"+de'n rd dudng rece'rerj free reecter +dpr.

d.

An individual qualified in radiation protection procedures shall be on site when fuel is in either reactor.*

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

  • SRO = NRC Senior Reactor Operator License RO = NRC Reactor Operator License
    • This shift 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 order to accommodate unexpected absence of personnel, provided immediate action is taken to restore the shift makeup to within the i

minimum requirements.

  • A unit is considered to be operating when it is in a mode other than cold shutdown or refueling shutdown.

Unit 1 - Amendment No.-l.74 15.6.2-3 Jrur; E '"

' Unit 2 - Amendment No.-111

NPL 99-0057 j ' ' e Page 4 of 14 l

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Unit 2 - Amendment No.132 i

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NPL 99-0057'

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Page 5 of 14 15.6.3.3 In the event the position of Health Physicist is vacated and the proposed replacement does not meet all the qualifications of 15.6.3.2, but is determined to be otherwise well qualified, the concurrence of NRC shall be sought in approving the qualification of that individual.

.15.6.3.4 The Duty Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design and response and analysis of the plant for transients and accidents. The Duty Shift Technical Advisor shall also receive training in plant design and layout including the capabilities ofinstrumentation and controls in the control room.

15.6.3.5 The Operations Manager shall:

1)

Hold a Senior Reactor Operator license at PBNP; or 2)

Have held a Senior Reactor Operator license at PBNP or a similar unit; or 3)

Have been certified at an appropriate simulator for equivalent senior operator knowledge level.

If the Operations Manager does not hold a Senior Reactor Operator license at PBNP, then an operations middle manager to whom the operating crews report shall hold a Senior Reactor Operator license at PBNP.

Unit 1 - Amendment No.483 15.6.3-2 Unit 2 - Amendment No.482 M r e 24,!

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l NPL 99-0057 l

Page 6 of 14 i

1 15.6.4 TRAINING t-i l

15.6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Manager and shall meet or I

exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-l 1971 and 10 CFR Part 55.

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i 15.6.5 REVIEW AND AUDIT 15.6.5.1 Manager's Supervisory Staff DELETED, (Relocated to owner controlled i

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Unit 1 - Amendment No. R2 August 25, '

Unit 2 - Amendment No.14 15.6.6-1 i

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..NPL'99-0057

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r a re e Page 11 of 14 15.6.8 PLANT OPERATING PROCEDURES 1

l 15.6.8.1 The plant shall be operated and maintained in accordance with approved procedures..Mais pr^-MureProcedures, ru;;e*M by ep;-^;riete :eer ;--Murr (ru^. - 4 4e " "r*r, e7e.,a ; :...-a

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shall be provided for the following operations where these operations involve nuclear safety of the plant:

1.

Normal sequences of startup, operation and shutdown of components, systems and overall plant.

2.

Refueling.

3.

Specific and foreseen potential malfunctions of systems or components including abnormal reactivity changes, j

4.

Security Plan Implementation.

5.

Emergencies which could involve release of radioactivity.

6.

Nuclear core testing.

7.

Surveillance and Testing of safety related equipment.

8.

Fire Protection Implementation.

15.6.8.2 Approval of Procedures.

i A.

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;!e---+ "^- Each procedure, or change thereto, of the categories listed in 15.6.8.1 (except 15.6.8.1.4) and 15.6.11 shall be reviewed by an individual or group other than the individual who prepared the procedure, or change thereto. All procedures of the categories listed in 15.6.8.1 (except 15.6.8.1.4) and 15.6.11, and modifications to the intent thereof, shall be approved by the Plant Manager or a department manager assigned responsibility for those procedures (hereafter referred to as the Approval Authority) prior to implementation.

Non. intent changes shall be reviewed and approved in accordance with 15.6.8.2 or 15.6.8.3.

B.

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-d ep; c"M by *S "-- ;e. Individuals responsible for reviews in accordance with 15.6.8.2 and 15.6.8.3 shall be members of the plant staff previously designated by the Plant Manager and meet Unit 1 - Amendment No.-94 15.6.8-1

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Unit 2 - Amendment No. M

NPL 99-0057 m 4.

Page 12 of 14 i

or exceed the qualifications of Technical Specification 15.6.3.

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C.

Each review shall include a determination of whether or not additional, cross-disci linary review is p

necessarv. If deemed necessary, such review shall be performed by qualified personnel of the appropriate discipline.

4 D.

Each review shall include an assessment for applicability of 10 CFR 50.59 and when necessary 1

gpropr. ate evaluations shall be performed.

i 15.6.8 Plant Operating Procedures (Continued) 15.6.8.3 Changes to Procedures A.

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to the intent of the original procedures shall be approved in accordance with 15.6.8.2.

B.

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changes to procedures, of the categories listed in 15.6.8.2A, which do not change the intent of the a_pproved procedure, may be made provided such changes are approved by two members of the plant staff, at least one of whom holds a Senior Reactor Operator's License.

C.

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  • rcu _All temporary changes to procedures of the r

w r

r categories listed in 15.6.8.2A shall subsequently by reviewed and approved in accordance with 15.6.8.2 within 2 weeks. Temporary changes only become perm ment changes after approval by the Approval Authority.

Unit 1 - Amendment No.- M 15.6.8-2 "pril ??, 1995 Unit 2 - Amendment No. M

NPL 99-0057 g,

Page 13'of 14

'15.7.8 A1)MINISTRATIVE CONTROLS 15.7.8.1 DELETED N"-- 't: "---- ': e" :-t: ; c -" '

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1

.,a t 15.7.8.2 Audits A.

An audit of the activities encompassed by the Radioac'ir i Emuent and Materials Control and Accountability Program (REMCAP), [the Offsite Dose Calculation Manual (ODCM), the Radiological Effluent Control Program (RECP), the Radiologica! Environmental Monitoring Program (REMP), and the Process Control Program (PCP)] and its implementing procedures shall be performed utilizing either offsite licensee personnel or a consulting firm.

B.

The results of the audit above shall be transmitted to the Chief Nuclear Officer and the Chairman of the Offsite Review Committee.

15.7.8 3 Plant Operating Procedures and Programs The Radioactive Emuent and Materials Control and Accountability Program (REMCAP) shall be established, implemented, and maintained in accordance with the provisions of Technical Specification 15.6.8. REMCAP shall assure that radioactive effluent and waste material from PBNP complies with applicable Federal, State, and burial ground regulations while keeping all exposures to members of the public as low as reasonably achievable (ALARA). This program shall conform to and implement the requirements of PBNP GDC 70 and of 10 CFR 5034a and 10 CFR 5036a for the

. control ofradioactive effluents while maintaining doses from these effluents ALARA, shall implement the requirements of 10 CFR 5034a and General Design Criterion 60 of Appendix A to 10 CFR 50 to suitably control the release and the processing of waste materials, shall conform to the guidance of Appendix I to 10 CFR 50 and PBNP GDC 17 for the assessment ofradioactivity in the environs of PBNP, and shall include remedial actions to be taken whenever the program limits are exceeded. REMCAP shall be implemented and maintained under the procedures and methodologies specified in the four (4) manuals / programs listed below and supported, as required, by other procedures. Effluent and environmental rnonitoring shall be addressed in the Quality Assurance Program.

' Unit Amendment No.-484 15.7.8-1 Jul'/ 12, 199?

Unit 2 '- Amendment ' fo. 4,44 i

- - - -. = - -. _...

.NPL 99-0057

- w.2 Page 14 of 14 3.

Revisions shall become effective aRer re"!eu rd :~ep" 'c by Se

"- c;e' Supe-"!=rj ?""rd 'he approval %=f the Plant Manager.

==

g B.

Revisions to the EM, ODCM, RECM and REMCAP 1.

Revisions to the EM, ODCM, RECM and REMCAP shall be documented and reviews perfonned of the revision shall be retained as required in 15.7.8.6. The documentation shallcontain:

Sufficient information to support the change together with the appropriate a.

analyses or evaluationsjustifying the revision, and b.

A determination that the change will maintain the levels of radioactive effluent control required pursuant to 10 CFR 20.1302,10 CFR 50.36a, Appendix I to 10 CFR 50, and 40 CFR 190.

2.

Shall become effective aRer : "4" --d ?~cp"-~ by 3"-- ;e6 Frpe z!r rj 9""rd te approval of the Plant Manager.-SBNR, 3.

Shall be submitted to the Commission in the form of a complete, legible copy of the entire manual either as part of, or concurrent with, the Annual Monitoring Report for the period of the report in which the revision was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed. Each copy shall indicate the date (e.g.,

month / year) the revision was implemented.

4.

In addition to items 1-3 above, all changes regarding explosive gas must be made via the 50.59 process.

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Unit 1 - Amendment No.-444 15.7.8-7 Mly 12, 1999 Unit 2 - Amendment No. 444

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