ML19350E511

Proposed App a Tech Spec Section 6.0 Re Administrative Controls & App B Figures Reflecting Organization & Mgt Title Changes

ML19350E511
Person / Time
Site:	FitzPatrick
Issue date:	06/15/1981
From:	POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML19350E503	List: ML19350E502 ML19350E509 ML19350E511
References
NUDOCS 8106230207
Download: ML19350E511 (12)

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.. O ATTACHMENT I PROPOSED TECHUICAL SPECIFICATION CHANGE RELATED TO ORGANIZATON AND MANAGEMENT TITLE CHANGES POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 8106230 2 0 7

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FIGURE 5.2-1 .

! POWER AUTi!ORITY OF TIIE STATE OF NEW YORK

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PRESIDENT AND CHIEF OPERATING OFFICER-SAFETY REVIEW COMMITTEE SENIOR VICE PRES 5 ENT- EXECUTIVE VICE NUCLEAR GENERATION PRESIDi:NT AND CHIEF ENGINEER RESIDENT MANAGER MANAGER-RADIOLOGICAL DIRECTOR-ENVIRONMENTAL HEALTH AND SAFETY PROGRAMS STAFF STAFF Figure 5.2-2 Management Organization-Offsite Radiological Environmental James A. FitzPatrick Nuclear Power Plant Amendment No. 44

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6.0 ADMINISTRATIVE CONTROLS tions Administrative Controls are the are subject to management means by which plant opera-control. Measures specified in this section provide for the assignment plant organiza tion, staffing qualifications and of responsibilities, related re-

-quirements, review and audit mechanisms, procedural controls and reporting requirements. Each of these measures are neces-sary to ensure safe and efficient facility operation.

6.1 RESPONSIBILITY The the plant. Resident Manager is responsible for safe operation of During period.1 when the Resident Manager is un-available, the Superintencent of Power will assume his respon-sibilities. In the ev.ent both are unavailable, the Resident Manager may delegate this responsibility to other qualifiet supervisory personnel.

'to the Sr. Vice President Nuclear Generation,The Resident Manager as shown in reports dir Fig. 6.1-1.

6.2  ; PLANT STAFF ORGANIZATION The plant staff organization is shown graphically in Fig.

6.2-1 and functions as follows:

1. A licensed senior reactor operator shall be on site at all times when there is fuel in the reactor.

2. In addition to item 1 above, a licensed reactor operator shall be in the control room at all times when there is fuel in the reactor.

3. In addition to items 1& 2 above, a licensed reactsr operator shall be readily available on site whenev

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the reactor is in other than ccid condition.

4. Two licensed reactor operators shall be in the con-trol room during start-ups and scheduled' shutdowns.

5. A licensed senior reactor operator shall be respon-sible for within theallsite movement boundary. of new and irradiated fuel A licensed reactor ope will be required to manipulate or directly superv,rator ise the manipulation of the controls of all fuel moving equipment, except the reactor building crane. All fuel movements by the reactor building crane, except new fuel movements from receipt through dry storage, shall be under the direct supervision of a licensed reactor opera tor.

All fuel movements within the core shall be direct analyst group. a y) monitored by a member of the reactor AmendeIent No. 247 SEE NEXT PAGE FOR FOOTNOTE

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f.. [ Radiological safety

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Mechanical engineering s h. -Electrical enginecring-

i. fAdministrative controls and quality assurance practices .

j. ' Environment 1

k. Civil / Structural Engineering

1. - Nuclear? L'icensing Em. Emergency Planning

n. Other: appropriate fields associated with the unique characteristics'of c nuclear power plant MEMBERSHI P -

6.5.2.2' The SRC snall be composed of the following voting members:

Chairman: Director-Nuclear Design and Analysis-Vice-Chairman: Vice President-Quality Assurance l.

Member: Manager-Nuclear Technical Support Member: Manager-Radiological Health and Safety l Member: Senior Vice President-Nuclear Generation Morber: Director-Electrical Design and. Analysis

-Member: Director of Environmental Programs Member: Dire'ctor-Civil /Structura' Design and Analysis Membert Director-Mechanical Design and Analysis Member: Senior Inservice Inspection Engineer-Nuclear Technical Support Member: Manager-Nuclear Licensing Member: Senior Nuclear Engineer-Design and Analysis Member: - Manager-Nuclear Operations l ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by1the SRC Chairmant however, no more than two alternates shall participate as voting members in SRC activities at any one time.

CONSULTANTS 6.5.2.4 Cons '.tants shall be utilized as determined by the  ;

-SRC Chairman to provide expert advice to the SRC.

MEETINL PREQUENCY 6.5.'2.5 The SRC shall meet at least once per calendar quarter

, during the initial year of facilicy operation following initial fuel. loading and at least once per six months, thereafter.

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Amendment No. 50 251 .

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6.5.2.6 A quorum of SRC chn11 consiat of the Chairman or '

Vicc-Chairmen and aix mrmbars, including alternates. 1;c  ;

more than minor.t ty of the quorum shall have a direct line l

. responsibility for the operation of the plant.

REVIEW 6.5.2.7 The SRC shall review:

a. The safety evaluation for 2) changes to procedures, equipment or systems and 2) tests or experiments com-pleted under the provision of Section 50.59, 10 CFR, to vt.ity that such actions did not constitute an unreviewed safety question.

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

c.

Propcsed tes ts or experiments which involve an un-reviewed 10 CFR.

safety question as defined in Section 50. 59, d.

Proposed changes to Technical Specifications of this Operating License.

e.

Violations cf code, regulations, orders. Technical Specifications, license requirements, or of internal procedures significance, or instructions having nuclear safety f.

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

g.

Events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commission.

h.

All recognized indications of an unanticipated deficiency in some aspect of design or operation of saf ety related structures, systems, or components.

i.

Reports and meetings minutes of the Plant Operating Review Committee.

AUDIT 6.5.2.8 Audits of f acility activities shall be performed under the cognizance of the SRC. These audits shall encompass:

a.

The conformance of f acility operation to provisions contained within the Technical Specifications and applicable months.

license conditions at least once per 12

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

Alendment No. f6

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c. Th3 r5culto of 6.tiona taksn to .cerrcet daficicncisa occurring in fecility cquipm:nt, otructuroc, cyatcm; i er m0thod cf cparction that hffset nuclor.r cafety et least once per 6 months.

d.

The-performance of activities required by the opera-

.tional Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months.

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

f. The Facility Security Plan and implementing procedures at least once per 24 months.

9 Any other area of facility operation considered appropriate by the SRC or the President.

h. The Facility Fire Protection Program and implementing procedures at least once per two p'ars.

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

j. 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.

AUTHORITY 6.5.2.9 The SRC shall report 'co and advise the President and Chief Operating Officer (to be referred to in the Tech Spec. as the President) on those areas of responsibility specified in Section 6.5.2.7 and 6.5.2.8. ,

RECORDS 6.5.2.10 Records will be maintained in accordance with ANSI 18.7-1972. The following shall be prepared, approved and distributed as indicated below:

a. Minutes of each SRC meeting shall be prepared, approved and forwarded to the President within l 14 days after the date of the meeting,

b. Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the President within 14 days following completion of the review.

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c. Audit reports encompassed by Section G.5.2.8 above, shall be forwarded to the President and l to the management positions responsible for the areas audited within 30 days after completion of the audit.

Amer.dr.ent No. 252a N

- ' CHARTER

.6.5.2.11 with a' charter approved by theConduct'of thm committee will be in a President setting forth the mechanism for implementation of the committee's responsibilities and authority.

6.6 REPORTABLE OCCURRENCE ACTION (A) In the event of a Reportable Occurrence, the NRC shall be of Specification 6.9. notified and/or a report submitted pursuant to t (B)

Each Reportable Occurrence requiring 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the NRC shall be revie.?ed timely by. tFL- PORC and a report submitted by the Resident Manager to the Senior Vice President-Nuclear Generation and the SRC.

6.7 SAFETY-LIMIT VIOLATION (A) If a safety limit is exceeded, the reactor shall'be shut downthe with and reactor. operation provisions of 10 CFR shall only be resumed in accordance 50.36 (c) (1).

(B) be made to the NRC by the Resident Manager.An The Senior Vice immed President-Nuclear notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Generation and Chairman of the SRC will be (C)

The PORC shall prepare a complete investigative report of and evaluation of:each (1) safety limit violation and include appropriate anal occurrence, (2) applicable circumstances preceding the systems or structures andeffects (3) of the occurrence upon facility componen prevent recurrance. corrective action r-equired to report The Resident Manager shall forward this of the SRC and the NRC.to the Senior Vice President-Nuclear Generation, Ch c 6.8 PROCEDURES (A)

Written procedures established, and adminstrative policies shall be implemented and maintained that meet or exceed the requirements and recommendations of Section 5 "Facitity Administrative Policies and Procedures" of ANSI Appendix A of Regulatory Guide 1.33, November 1972.18.7-1972 In and addition, procedures shall be established, implemented and maintained for the Fire Protection Program.

(B)

Those procedures affecting nuclear safety shall be reviewed by PORC and approved by the Resident Manager prior to implementation.

(C) provided:Temporary changes to nuclear related procedures may be made 1.

-The intent of the original procedure is not altered.

AmenmentNo,f 253

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• DIRECTOR OF SAFETY AND FIRE PROTECTION RESIDENT w MANAGER w PROCEDURES AND PERFORMANCE

' tThe Senior the fire Vice President protection program.Nuclear Generation is responsible for administering

• The Director of Safety and Fire Protection is the off-site management position responsible for assessing the effectiveness of the fire protection programs by conducting reviews and audits.

FIGURE 6.1-1 MANAGEMENT ORGANIZATION CilART r JAMES A.

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SAFETY EVALUATION RELATED TO ORGANIZATION AND' MANAGEMENT TITLE CHANGES S

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i POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO.-50-333 s

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, .Szction I2- Daccription of Modifiention

The modification seeks to revise-the Section 6.0 Administrative Controls of.. Appendix-A by:

.1) . changing'the~ titles'of several membersiof the Safety. Review Committee-(SRC),.

2) adding the Manager-Nuclear Operations to the membership of Lthe-SRC=and increasing the quorum requirements,

3) adding Emergency Planning as a new area of SRC competence,

4) Jdeleting the position of Executive Vice President and Director of Power' Operations-from the Management Organizational Chart

-(Figure.6.1-1),

5) , changing the titles of several positions shown on the Manage-ment Organizational Chart (Figure 6.1-1),

6) changing;the reporting requirements of the Senior Vice President Nuclear' Generation and the Safety Review Committee to the President and Chief Operating Officer,

7) ~

adding the position of Executive Vice President-Procedures and Performance to the Management Organizational. Chart (Figure 6.1-1)-

and-the Director of. Safety and Fire Protection who is responsible for the Power Authority direction of the Fire Protection Program,

8) changing the title of several positions shown on the Plant Staff Organizational Chart (Figure 6.2-1), correction of a typographical crror for the Nuclear Control Operators position and addition of the Shift Technical Advisor.

The modification Contols of Appendix seeks B.by:to revise Section 5.0 Administrative

1) correcting. typographical errors on Figure 5.2-1 Plant Organization to reflect the fact that this chart is for the radiological environmental program only,

2) to correct organizational responsibilities and reporting r'equire-

~nents and title changes in Figure 5.2-2 as described in Items 4 and 6 above,

3) to reflect the fact that this chart is for the radiological environmental program only by the deletion the Director-Environ-mental Programs and the addition of.the Manager-Radiological Health and Saf,ety.

Section II Purpose of Modification

~The purpose of this modification is to update the Section 6.0 Administrative Controls and-the organization figures of Appendix B, Section 5 to reflect recent organization and management title changes which have taken place at the Authority.

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i I Section III- Impact of the Change These modifications will not alter the conclusions reached in

,the FSAR and SER accident analysis.-

Section~IV - Implementation of the Modification The modifications as proposed will not impact'the ALARA or Fire Protection' Program at JAF.

Section V - Conclusion The incorporation of these modifications: a) will not increase the probability nor the consequences of an accident or mal-function-of equipment important to safety as previously evalu-ated in the Safety Analysis Report; b) will not increase the possibility for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report; and c) will not reduce the margin of safety as defined in the basis for any Technical Specification, and d) does not constitute an unreviewed safety question.

Section'VI - References (a) JAF PSAR (b) JAF.SER

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