ML20091J386

Proposed Tech Specs Reflecting Organizational & Personnel Changes Re Operational & Review Responsibilities

ML20091J386
Person / Time
Site:	Peach Bottom
Issue date:	05/29/1984
From:	PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20091J358	List: ML20091J354 ML20091J372 ML20091J386
References
NUDOCS 8406050493
Download: ML20091J386 (12)

Text

- _ _ .

i SHOWN FOR INFORMATION i

! PURPOSES ONLY NOT A i BOARD OF DIRECTORS

PART OF THE OPERATING :

i LICENSE i l

j CHAIRMAN OF THE BOARD & i

~~

i CHIEF EXECUTIVE OFFICER i

-'i i '

., i PRESIDENT & i y i CHIEF DPERATING OFFICER i o  :  :

' i i

I i  :

l l A NUCLEAR g ELECTRIC NUCLEAR  !

POWER --------- PRODUCTION --------

REVIEW i SR. VICE PRESIDENT VICE PRESIDENT BOARD  !

i

! I i i NUCLEAR i j PRODUCTION  !

MANAGER j i

t n 1 I

I I QUALITY ASSURANCE NUCLEAR GENERATION DIVISION DIVISION SUPERINTENDENT #

SUPERINTENDENT ,

REPORTIN3 ?ES?SNSIBILITY  :

A CHIEF EXECUTIVE OFFICER ~

l O CHIE: 0?ER.tTIME OFFICER SUPT. PEACH BOTTOM

? RES?ONSIBLE FOR OVERALL NUCLEAR SERVICES STATION SU?T.

FIRE PROTECTION PROGRAM l MANAGEMENT ORGANIZATION CHART PHILADELPHIA ELECTRIC COMPANY so493 s ppADOCK05 p CH BOTTdu ATOMIC POWER STATION - UNITS 2 AND 3 PDR FIGURE S.2-1

, . 6-l PBAPS '

6.3 Facility _8taff_ Qualifications L 6.3.1 Bach member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the Senior Health Physicist (Radiation Protection Manager) who shall meet or exceed the qualifications of Regulatory Guide 1.8,

September 1975 and (2) the shift Technical Advisor who shall have "a' bache' lors 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.

6.4 Training 6.4.1 A retraining and replacement training program for the facility staff shall be raintained under the direction l- of the Station superintendent and shall meet the i

requirements of Section 5.5 of ANSI N.18.1-1971 and 10 .

CPR 55, Appendix A.

l 6.4.2 A training program for the Fire stigade shall be conducted such that Fire Srigade members complete an instruction program within a two year period. Regularly planned meetings will be held every 3 months.

l j 6.5 Review gnd Audit l 6.5.1 HIME 5gir3EToT aeview Committee y nc.),

i Function l 6.5.1.1 THi FIIHt Operation Review Committee shall function to advise the station superintendent on all matters related L to nuclear safety.

l Composition l

6.5.1.2 THE PI5HE Operation Review Committee shall be composed

• of ther j n Station superintendent - Chairman station Assistant superintendent Engineer - Technical Engineer - Maintenance Engineer - Operations Engineer - Results Engineer - Reactor Engineer - Instrument & Control i Senior Health Physicist Engineer - Outage Manager Sh;,f t Superintendent l i

i Alternates 4.5.1.3 XIEirHIEi~ members shall be appointed in writing by the PORC Chairman to serve on a temporary basist however, no more than two alternates shall participate in PORC activitten at any one time.

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PBAPS Meeting Frequency 6.5.1.4 The PORC shall meet at least once per calendar month and as convened by the PORC Chairman.

Quorum 6.5.1.5 A quorum of the PORC shall consist of the Chairman ,

and four members or their alternates.

Responsibilities 6.5.1.6 The Plant Operation Review Committee shall be responsible for

a. Review of 1) all procedures required by Specification 6.8 and changes thereto, 2) any other proposed procedures or changes thereto ,

as determined by Station Superintendent to affect nuclear safety.

b. Review of all proposed tests and experiments that affect nuclear safety.

c. Review of all proposed changes to the Technical Specifications.

d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.

e. Investigation of all violations of the Technical Specifications and shall prepare and forward a report covering evaluation and recommendations to prevent recurrence to the Superintendent, Nuclear Generation Division and the Chairman of the Nuclear Review Board. ,

f. Review of' facility operations to detect potential safety hazards.

- g. Performance of special reviews and i investigations and reports thereon as

. requested by the Chairman of the Nuclear l

Review Board.

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e

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PBAPS '

6.5.1.6 Continued

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h. Review of the Plant Security Plan and -

implementing procedures, and shall submit recommended changes to the Plan to the Chairman of the Nuclear Review Board,

i. Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Plan to the Chairman of the Nuclear Review Board.

Authority 6.5.1.7 The Plant Operation Review Committee shall

a. Recommend to the Station Superintendent wri tten approval or disapproval of items considered under 6.5.1.6(a) through (d) above,

b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question, as defined in 10 CFR 50.59.

c. Provide immediate written notification to the Superintendent, Nuclear. Generation Division, or in his absence, the Superintendent, Nuclear Services, and the Nuclear Review Board of

. disagreement between the PORC and the Station Superintendent; however, the Station Superintendent shall have reponsibility for resolution of such disagreements pursuant to 6.1.1 above.

Records 6.5.1.8 The Plant Operation Review Committee shall maintain written minutes of each meeting and copies shall be l provided to the Superintendent, Nuclear Generation i Division, and Chairman of the Nuclear Review Board, i

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, PDAPS '

6.5.2 Nuclear Review Board Function 6.5.2.1 The Nuclear Review Board (NRB) shall function to provide independent review and audit of designated activities in the area of:

a. nuclear power plant operations

b. nuclear engineering

c. chemistry and radiochemistry

d. metallurgy

e. instrumentation and control

f. radiological safety

g. mechanical and electrical engineering

h. quality assurance practices -

The members of the NRB will be competent in the area of qdality assurance practice and cognizant of the Quality Assurance requirements of 10 CFR 50, Appendix D.

Additionally, they will be cognizant of the corporate Quality Assurance Program and will have the corporate Quality Assurance organization available to them.

Organi zati on 6.5.2.2 The Chairman, Members and alternate Members of the NRB shall be appointed in writing by the Vice President, Electric Production, and shall have an academic degree in an engineering or physical science field; and .in addition, shall have a minimum of five years technical experience, of which a minimum of three years shall be in one or more areas given in 6.5.2.1.

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PBAPS Altggnates ..

6.5.2.3 Each permanent member shall have a designated alternate to serve in his absence, and a current list of these alternates shall be maintained in NRB l records. Each alternate member will serve on a continuing basis.

Consultants 6.5.2.4 Consultants shall be utilized as determined by the NRB Chairman to provide expert advice to the NRB.

Meeting Freguency 6.5.2.5 The NEB shall meet at least once per six months.

Quorum 6.5.2.6 A quorum of the NRB shall consist of the Chairman -

or Vice Chairman or their designated alternates and four members or their alternates. No more than a minority of the quorum shall have line responsibility for operation of the facility.

Review 6.5.2.7 The NRB shall review:

a. The safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provision of 10 CFR 50.59, to verify that such actions did not constitute an unreviewed safety question.

b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59.

c c. Proposed tests or experiments which involve an i unreviewed safety question as defined in 10 CFR 50.59.

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., l PBAPS 6.5.2.7 Continued

'~

d. Proposed chan or Licenses. ges in Technical Specifications  !

Violations of applicable statutes, codes, e.

regulations, orders, Technical Specifications, o license requirements, or of internal procedures or instructions having nuclear safety significance,

f. Significant operating abnormalities or deviations f rom normal and expected performance of plant equipment that affect nuclear safety.

g. All events which are required by regulations or Technical Specifications to be reported to the NRC in writino within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. .

h. Any indication of an unanticipated deficiency in some aspect of design or operation of safety-related structures, systems, or compone nts ,

i. Reports and meeting minutes of the Plant Operation Review Committee.

Audit 6.5.2.8 Audits of facility activities shall be performed

under the cognizance of the NRB. These audits shall encompass

a. The conformance of facility operation to -

[ provisions contained within the Technical Specifications and applicable license l

conditions at least once per year.

b. The performance, training and quali ficationc of the entire facility staff at least once per year.

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

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.s .

~

PBAPS

6.5.2.8 Continued .

d. The performance or activities required by the Quality Assurance Program to meet the criteria of 10 CFR 50, Appendix D, at least once per two years.

e. The Facility Emergency Plan and implementing procedures at least once per two years.

f. The Facility Security Plan and implementing procedures at least once per two years.

g. Any other area of facility operation considered appropriate by the NRB or the Vice President, Electric Production. l Authority 6.5.2.9 The NRB shall report to and advise the Vice President, Electric Production, on those areas of l

responsibility specified to Section 6.5.2.7 and 6.5.2.8.

Records 6.5.2.10 Records of NRB activities shall be prepared, approved, and distributed as indicated below:

a. . Minutes of each NRB meeting shall be prepared, approved and forwarded to the Vice President, Electric Production, within 10 working days following each meeting.

b. Reports of reviews encompassed by Section 6.5.2.7.e, f, g and h above, shall be prepared, approved and forwarded to the Vice President, Electric Production, within 10 working days following completion of the review.

c. Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Vice President, Electric Production, and to the management positions responsible for the areas audited within 30 days after completion of the audit.

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e PBAPS '

6.6 Reportable Occurrence Action -

, 6.6.1 The following actions shall be taken in the event of a Reportable Occurrence

a. The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.

b. Each Reportable Occurrence Report submitted to the Commission shall be reviewed by the PORC and submitted to the NRB and the Superintendent, Nuclear Generation Division.

6.7 Safety _ Limit Violation 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a. The provisions of 10 CFR 50.36 (c) (1) (i) -

shall be complied with immediately.

b. The Safety Limit violation shall be reported to the Commission, the Superintendent, Nuclear Generation Division or, in his absence, the Superintendent, Nuclear Services and to the NRB immediately.

c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PORC. This. report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

d. The Safety Limit Violation Report shall be submitted to the Commission, the NRB and the Superintendent, Nuclear Generation Division within 10 working days of the violation.

6.8 Procedures 6.8.1 Written procedu'res and administrative policies shall be established, implemented and maintained that meet the requirements of Sections 5.1 and 5.3 o'E ANSI N18.7-1972 and Appendix "A" of USAEC Regulatory Guide 1.33 (November 1972) except as provided in 6.8.2 and 6.8.3 below.

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c In cddition to the responsibilities spacified in Appendix A to the Operating License, the safety review committees shall have the following responsibilities concerning the environmental impact of the plant. -

c A. Plant Operation Reyiew Committee (PORC) ,

1. Review proposed on-site tests and experiments and results thereof, when such tests have environmental significance.

2. Review propsed changes to the environmental technical specifications.

3. Review operating instructions as specified in Section 7.3.3.

4. Review environmental deviations as specified in Section 7.2.3.

B. Nuclear Review Board (NRB)

1. Review proposed changes to the environmental technical specifications.

2. Review proposed changes or modifications to plant systems or equipment which may affect the environmental impact of the plant.

3. Conduct periodic audits of plant operations.

4. Review all reported environmental deviations.

7.2 Action to be Taken if a Protection Limit or Rep ~ ort Level is Excii333'Br Il~Eirmful Ellicts 6Etecte3~~~~~~~

~~~

7.2.1 For the purpose of this specification an environmental deviation shall be considered as defined in Section 1.0.

7.2.2 Any environmental deviation shall be reported

- immediately the Superintendent, Nuclear Generation Divisica or, in his' absence, the Superintendent, Nuclear Services, and promptly reviewed by the Plant Operations Review Committee. This Committee shall prepare a separate repor't for each environmental

- deviation. This report shall include an evaluation of the cause of the deviation, the extent and magnitude of the impact, and recommendations for appropriate action to prevent or reduce the probability of such a deviation.

m,_._

e i.2.3 ,

copies of all such reports shall be submitted to the Superintendent, Nuclear Generation Division, and to the Chairman of the Nuclear Review Board for review and approval of any -

recommendations.

7.2.4 The Superintendent, Nuclear Generation Division, shall report the circu,nstances of any environmental deviation to the NRC as specified in Section 7.4.2.

7.2.5 If harmful effects or evidence of irreversible damage not considered in the Final Environmental Statement are detected by the monitoring programs, the licenses will provide to the staff an analysis of the problem and a plan of action to be taken to eliminate or significantly reduce the detrimental effects or damage.

7.3 Unit _ Operating Procedures 7.3.1 The plant personnel shall have available instructions for use in the anticipated operation of the plant components and systems that could have an impact on the environment.

7.3.2 Instructions and appropriate check-off lists shall be

provided for the following

A. Normal start-up, operation, and shutdown of systems and components involving the environmental aspects of the plant.

B. Actions to be taken to correct specific and foreseen potential malfunctions of systems or components involving the environmental aspects of the plant.

C. Surveillance and testing requirements of environmental monitoring equipment associated with the monitoring requirements of Section 3.0 of these ETS.

7.3.3

! All instructions described under 7.3.1 and 7.3.2, and changes thereto, shall be reviewed and approved by the Plant Superintendent prior to implementation. .

~7.3.4 Temporary changes to instructions, which do not change the intent of the original instruction, may be made provided such changes are approved by the Shift Superintendent-and one other mrmber of the POR Committee. Such changes 95all be documented L and subsequently reviewed by the Plant Supet ntendent.

l i SHOWN FOR INFORMATION i, PURPOSES ONLY NOT A :

l  ; BOARD OF DIRECTORS PART OF THE OPERATING i j LICENSE l i i

l CHAIRMAN OF THE BOARD 8 l

l CHIEF EXECUTIVE OFFICER i*

i i PRESIDENT &  :

i CHIEF OPERATIt!C CFFICER j

I  :

I  :

E j A NUCLEAR ELECTRIC g NUCLEAR  !

Y j POWER ------- -

PRODUCTION --------

REVIEW  !

1 SR. VICE PRESIDENT VICE PRESIDENT BOARD j I

l ll NUCLEAR i ll PRODUCTION j l MANAGER l J I I QUALITY ASSURANCE NUCLEAR GENERATION DIVISION DIVISION SUPERINTENDENT SUPERINTENDENT #

REPORTING RESPONSIBILITY A CHIEF EXECUTIVE OFFICER l

O CHIEF OPERATING OFFICER PEACH BOTTOM SUPT.

1. RESPONSIBLE FOR OVERALL NUCLEAR SERVICES STATION SUPT.

FIRE PROTECTION PROGRAM iMANAGEMENT ORGANIZATION CHART PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION - UNITS 2 AND 3

, FIGURE 7.1-1