ML20086P656

Proposed Tech Specs Re Replacement of title-specific List of PORC Members W/More General Statement of Membership Requirements

ML20086P656
Person / Time
Site:	FitzPatrick
Issue date:	07/21/1995
From:	POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20086P633	List: JPN-95-034, Forwards Application for Amend to License DPR-59.Amend Would Replace title-specific List of Members on PORC W/More General Statement of Membership Requirements ML20086P642 ML20086P656
References
NUDOCS 9507270088
Download: ML20086P656 (12)

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JAFNPP 6.0 ADMINISTRATIVE CONTROLS .

Administrative Controls are the means by which plant operations are subject to mancgement control. Measures specified in this section provide for the assignment of - .

responsibilities, plant organization, staffing qualifications and related requirements, review l and audit mechanisms, procedural controls and reporting requirements. Each of these measures are necessary to ensure safe and efficient facility operation.

6.1 RESPONSIBILITY -

Sh Exe N j The6sident Mana'nelr i ible for safe operation o lant. During periods  ;

unavailable, one of the three Ge l Managers will  ;

when the%ident Managt assume this responsibility. In the event all four are unavailable, thebsidsnt Mana f may delegate this responsibility to other qualified supervisory personnel.

6.2 ORGANIZATION U

6.2.1 Facility Manaoement and Technical SuDDort Onsite and offsite organizations shall be established for plant operation and corporate 'I management, respectively. The onsite and offsite organizations shall include the positions for activities that affect the safety of the nuclear power plant.

1. 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 department responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be doeurnented in the Updated FSAR.

- Site Executive Officer

2. Thekident Manaqq shall be responsible for overall plant operation, and shall have control over thossT>nsite activities that are necessary for safe operation and maintenance of the plant.

3. Th xecutive Vice President and, hief Nuclear Officer shall take any measures neede 51nsure acceptable, performance of the staff in operating, maintaining, and i providing technical support to the plant to ensure nuclear safety.

4. The individuals who train the operating staff and those who carry out health physics and quality aesurance functions may report to the appropriate onsite manager; however, they sindi have sufficient organizational freedom to ensure their l independence from operating pressures.

6.2.2 Plant Staff The plant staff organization shall be as follows: j

1. Each shift crew shall be composed of at least the minimum shift crew composition shown in Table 6.21; l

Amendment No. -60r60r78r111,130.137,178, 203, 220-247- l 95072700g3 950721 DR I

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2. An SRO or an SRO with a license limited to fuel handling shall directly supervise all Core Alterations. This person shall have no other duties during this time;

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. 4. In the event of illness or unexpected absence, up to two (2) hours is allowed to restore the shift crew to the minimum complement. l Shift Manager,and Control Room Supervisor l h The Operations Manager, Assistant Operations Manag 68%upervisor and AssW >

[S.iSJh Myn shall hold +,SRO license and the Senior NucTe~ar vpemiur ano Ine Nuclear Control Operator shaU hold,+ RO license or an SRO license.

6. Administrative procedures sha developed and implemented to limit the working hours of unit staff who perform safety-related functions; e.g., senior reactor operators, health physicists, auxiliary operators, and maintenance personnel who are working on safety-related systems.

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

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

a. 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,

b. 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 seven day period, all excluding shift turnover time.

c. A break of at least eight hours should be allowed between work periods, including shift turnover time.

d. Except during extended shutdown 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 guidelines shall be authorized by the@ident Mangibor the General Manager - Operations, or higher levels of management, in accordance with established procedures and with documenta n of the basis for granting the deviatiolt.

Controls shall be included in the procedu that individual overtime shall be reviewed monthly by the6sident,Mana r his designee to assure that excessive hours have not been assigned. Routinejdeviation from the above guidelines is not authorized.

Site Executive Officer Site Executive Officer Amendment No. 40,111,130,437,179,100,219 247a

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JAFNPP 6.3 , PLANT STAFF QUALIFICATIONS 6.3.1 The minimum qualifications with regard to educational background and experience for plant staff positions shown in FSAR Figure 13.2-7 shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions; except for the Radiological

! and Environmental Services Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.

- 6.3.2 The Shift Technical Advisor (STA) shall meet or exceed the minimum requirements of either Option 1 (Combined SRO/STA Position) or Option 2 (Continued use of STA Position), as defined in the Commission Policy Statement on Engineering Expertise on Shift, published in the October 28,1985 Federal Register (50 FR 43621). When invoking Option 1, the STA role may be filled by the<StliftsuDervisor or Assistant tinsp C,~i i" (1) l Shift Manager or Control Room Supervisor -T 6.3.3 ' Any deviations will be justified to the NRC prior to an individuars filling of one of these positions.

NOTE:

(1) The 13 individuals who hold SRO licenses, and have completed the FitzPatrick Advanced Technical Training Program prior to the issuance of License Amendment 111, shall be considered qualified as dual-role SRO/ STAS.

6.4 RETRAINING AND REPLACEMENT TRAINING A training program shall be maintained under the direction of the Training Manaper to assure overall proficiency of the plant staff organization. It shall consist of both retraining and replacement training and shall meet or exceed the miniinum requirements of Section 5.5 of ANSI N18.1-1971.

The retraining program dall not exceed periods two years in length with a cuniculum designed to meet or en.wed the requalification requirements of 10 CFR 55.59.

6.5 REVIEW AND AUDIT Review requirements are completed by using designated technical reviewers / qualified safety reviewer and two separate review committees. The Plant Operating Review Committee (PORC) is an onsite review group; the Safety Review Committee (SRC) is an independent offsite review and audit group.

6.5.0 REVIEW AND APPROVAL OF PROGRAMS AND PROCEDURES 6.5.0.1 The procedure review and approval process shall be controlled and implemented by administrative procedure (s).

6.5.0.2 Each program and procedure required by Specification 6.8 and other procedures that affect nuclear safety, and changes thereto, shall be reviewed by a minimum of two designated technical reviewers who are knowledgeable in the affected functional area.

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. Amendment No.-22r34r67r09r441r134r437r478r4907 21Sr 222--

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' 6.5.0.3 Designated technical reviewer (s) shall meet or exceed the qualifications described in Section 4 of ANSI N18.1-1971 for applicable positions, with the exclusion of the positions identified in Sections 4.3.2 and 4.5. Individuals whose positions are '

described in Sections'4.3.2 and 4.5 may qualify as designated technical reviewers provided they meet the qualifications described in other portions of Section 4.

6.5.0.4 The designated technical reviewer shall determine the reeed for cross-disciplinary reviews. Individuals performing cross disciplinary reviews shall meet or exceed the quellfications described in Section 4 of ANSI N18.1-1971 for applicable positions.

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' 6.5.0.5 L Each program and procedure required by Specification 6.8 and other procedures

that affect nuclear safety, and changes thereto, shall be reviewed from a safety l

perspective by a qualtied safety reviewer. Safety and/or environmentalimpact -

evaluations, when required, shall be reviewed by PORC per Specification 6.5.1.6.a.

16.5.0.6 (Nuclear safety related procedures and procedure changes shall be reviewed and  ;

' approved, prior to implementation, by the appropriate member (s) of management.

6.5.1. PLANT OPERATING REVIEW COMMITTEE (PORC) i l

6.5.1.1 Function (Site Executwo Officer l i

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PORC shall function to advise the Relide'nt Mana qDon matters related to nuclear safety and environmental impact. ,

6.5.1.2 Membership - l lant Operating Review Committee shall be composed of the:

Replace with INSERT "A" j Chairman: General Manager - O tions i Vice-Chairman /Mem General Manage upport Services  !

Vice-Chairman / Member: General Ma r - Maintenance Member: Opera ' Manager '

Member: M nance Manager hnical Services Manager  :

Member;  !

Member: Ins ont and Controls Manager Member:' Radio I and Environmental '

Services Ma r i

Site Engineering - ager Member:

Member: R~eactor Analyst Supe ' r t nsultants to provide expert advice may be utilized when the na of a Spec' ular problem dictates. .

INSERT "A"

The Plant Operating Review Committee shall be composed of a Chairman, Vice-Cha irmen ,

and members designated in writing by the Site Executive Officer. Members shall or lectively have responsibility in at least the areas of Operations. Maintenance, Radiological und Environmental Services, Engineering, Reactor Engineering, instrumentation and controls, l Nuclear Licensing,'and Quality Assurance.

Amendment No. --34 7 67,170,222-248a r

'JAFNPP 6.5.1.3 Alternates Alternate members shall be appointed in writing by the PORC Chairman to serve on a temporary basis. l 6.5.1.4 - Meeting Frequency l

Meetings will be. called by the Chairman as the occasions for review or investigation arise. . Meetings will be no less frequent than once a month.

6.5.1.5 Quorum l la I A quorum of the PORC shall consist of the Chairman or x :f i Vice-Chairm n and five members including designated alternates. Vice-Chairmen may act as members.

when not acting as Chairman. A quorum shall contain no more than two alternates. l 6.5.1.6- Responsibilities The PORC shall be responsible for the:

a. Review of 10 CFR 50.59 safety evaluations including those associated with procedures and programs required by Specification 6.8, and changes thereto.

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

c. Review of proposed changes to the Operating License and Technical Specifications.

d. Review of propcsed changes or modifications to plant systems or equipment that affect nuclear safety. 3h Faecutive ONicer l

e. Investigations of violations to the/rech al Specifications. The PORC shall prepare and present a report coygrinatthe e ~

ions and recommendations to prevent j recurrence to the (fe~s_ident Mana A who will then forward the report to the utive Vice President arLttcfilef Nuclear Officer, the Vice President Regulatory Affalit eTrund torttWCfisiiirman of the Safety Review Committee,

f. Review of plant operations to detect potential safety hazards.

Performanna af anacial raviaw= and/r>r investigations at the request of the Resi n'y anapdp Site Executive Officer.

h. Review of all reportable events.

i. Review of the Process Control Program and the Offsite Dose Calculation Manual (ODCM) and changes thereto.

J. Review the FitzPatrick Fire Protection Program and implementing procedures and

- changes thereto.

[ ;. Amendment No. 22,07, ^A,170,222 249 p

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JAFNPP 6.5.1.7 Authority The PORC shall: Site Executive Officer

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a. Recommend to the(e'sident Managqn approval or disapproval of those items reviewed under Specifications UK1.6.a through 6.5.1.6.d.

b. Render determinations with regard to whether or not iterns considered under Specification 6.5.1.6.a through 6.5.1.6.e constitute an Unreviewed Safety Question as defined in 10 CFR 50.59.

c. In the event of a disaareebtween the PORC and16sident Manajst, notify thedEiiecutive Vice-President idRbChief Nu at Officer andW C' Chairman , or their designated afternates, within 24 hou provide writte notification by the next business day. The6csTdenITWlalgegshall have resporpibility for resolution of such disagreement pursuant to Section G'.A /

Site Executive Officer 6.5.1.8 Records Minutes of all meetings of the PORC shall be recorded and numbered. Copies will be retained in file. Copies will be forwarded to the Chairman of the SRC and the ecutive Vice PresidentDChief Nuclear Officer.

6.5.1.9 Procedures Conduct of the PORC and the mechanism for implementation of its responsibilities and authority are defined in the pertinent Administrative Procedures.

6.5.2 SAFETY REVIEW COMMITTEE (SRC)

FUNCTION 6.5.2.1 The SRC shall function to provide independent review and audit of designated i activities in the areas of: i l

a. Nuclear power plant operations i

b. Nuclear engineering

c. Chemistry and radiochemistry

d. Metallurgy

e. Instrumentation and control Amendment No. 50, 70, 90, 94,110,218,220,222 250

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f. Radiological safety

g. Mechanical engineering

h. Electrical engineering

1. Administrative controls and quality assurance practices

- J. Environment

k. Civil / Structural Engineering

1. Nuclear Licensing

m. Emergency Planning

n. Other appropriate fields associated with the unique characteristics of a nuclear power plant CHARTER 6.5.2.2 The conduct of thC will be in accordance with a charter approved by the C ::i:

CVice President ant $ Chief Nuclear Officer. The charter will define the SRC's authority and establish the mechanism for canying out its responsibilities.

MEMBERSHIP 6.5.2.3 The SRC shall be composed of at least six individuals including a C pirman and a Vice Chairman. Members shall be appointed by the Vice President RegdlMery Affairs and Special Projects and approved by thetEihtcutive Vice President __glitbChief Nuclear Officer. SRC members and attemates shall have an academic degree in engineering or a physical science, or the equivalent, and shall have a minimum of five years technical ,

experience in one or more areas listed in Section 6.5.2.1.

f ALTERNATES ,

6.5.2.4 Alternates for the Chairman, Vice Chairman and members may be appointed in writing by the Vice President Regulatory Affairs and Special Projects and approved by the O NAcutive Vice President ant > Chief Nuclear Officer.

/ 1 CONSULTANTS  ;

6.5.2.5 Consultants may be used as determined by the SRC Chairman and as provided for in the charter.

MEETING FREQUENCY 6.5.2.6 The SRC shall meet at least once per six months.

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l Amendment No. -50r60r66r78r04,-400r106r423r202, 220 a

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c. ' The results of actions taken to correct deficiencies occurring in facility equipment, - "

structures, systems or method of operation that affect nuclear safety at least once  ;

per 6 months. j

d. - The performance of activities required by the Operational Quality Assurance Program j

- to meet the criteria of Appendix TB",10 CFR 50, at least once per 24 months.

'l e.1 Any other aram of femuv operation consider 6d appropnate by the SRC or the +

ecutive Vice President Ja > Chief Nuclear Officer.

f. The Facility Fire Protection Program and implementing procedures at least once per .

two years.

g. An independent fire protection and loss of preventicabspection and audit shall be .

performed annually utilizing either qualified offsite licensee personnel or an outside  !

fire protection firm.  ;

h. An inspection and audit of the fire protection and lors preve' ntion program shall be l  ;

performed by an outside qualified fire consultant ai. intervals no greater than 3 years.

l. The Radiological Environmental Monitoring Program and the results thereof at least l l t

once per 12 months.

J. : The Offsite Dose Calculation Manual and implementing procedures at least'once per l 24 months. .

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k. The Process Control Program and implementing procedures.for processing and l  !

packaging of radioactive wastes at least once per 24 months.

1. The performance of activities required by the Quality Assurance Program to meet the l' j provisions of Regulatory Guide 1.21. Revision 1. June 1974 and Regulatory Guide l s

4.1, Revision 1, April 1975 at least once per 12 months. j I

AUTHORITY l I

6.5.2.10 The SRC shall advise the<iiicutive Vice PresidentDChief Nuclear Officer on those areas of responsibility specmea in secnon 6.5.2.8 and 6.5.2.9.

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I Amendment liOrSO, "", 78r93rO4r220;-222-

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, I JAFNPP 6.53 RECORDS Records will be maintained in accordance with ANSI 18.7-1972. The following shall be prepared end distributed as indicated below:

a. Minutes of each SRC meeting shall be prepared and forwarded to the6ecutive VD O & resident al2bChief Nuclear Officer within 30 days after the date of the meeting. l

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b. Reports of reviews encom====d bv Section above shall be prepared and forwarded to thenacutive Vice President Chief Nuclear Officer within 30 days following completion of the review.

c. Audit renorts encompassed by Section 6.5.2.9 above, shall be forwarded to the Ex:f; '

GC37 ice President ali5 Chief Nuclear Officer and to the management positions responsible for

/ the areas audited within 30 days after completion of the audit.

Amendment No. 93r202,2r 252b

E JAFNPP 6.6 REPORTABLE EVENT ACTION The following actions shall be taken for Reportable Events:

(A) The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and (B) Each Reportable Event shall be reviewed by the POR he results of this review shall be subrnitted to theCiecutive Vice President a5st: Chief Nuclear Officer, the Vice President Regulatory Affairs and special Projects, and the Chairman of the SRC.

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

(B) An immediate report h safety limit violation sh made to the NRC by ()

the Eiisident Man essracutive Vice President and> Chief Nuclear Officer, the Vice President Regulatory and Special Projects, and the Chairman of the SRC will be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Site Executive Officer (C) The PORC shall prepare a complete invest' ative report of each safety limit violation and include appropriate analysis nd evaluation of; (i) applicable circumstances preceding the occurrence, 2 effects of the occurrence upon facility component systems or structure corrective action required to prevent recurrence. The@ident Man shall forward this report to the xecutive Vice PresidentRDChiet Nuclear Officer, the Vice President Regulatory Affairs and special Projects, the Chairman of the SRC, and the NRC. .

6.8 PROCEDURES (A) Written procedures and administrative policies shall be established, implemented, and maintained that:

1, meet or exceed the requirements and recommendations of section 5 of ANSI 18.7-1972 " Facility Administrative Policies and Procedures."

2. are recommended in Appendix A of Regulatory Guide 1.33, November 1972.

3. implement the Fire Protection Program.

4. include programs specified in Appendix B of the Radiological Effluent Technical Specifications, Section 7.2.

(B) Each procedure of Specification 6.8.(A), and changes thereto, shall be approved i prior to implementation by the appropriate responsible member of management as specified in Specification 6.5.0.

Amendment No. 507 60r65r78r03r440r222,222 253

JAFNPP 6.11 (A) High Radiation Area

1. In lieu of the " control device" or " alarm signal" required l by paragraph 20.203(c) (2) of 10 CFR 20, each High Radiation  !

Area (i.e.,2100 mrem /hr)in which the intensity of radiation is 1000 mrem /hr or less shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP).* Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. A radiation monitoring device which continuously indicates the radiation dose rate in the area.

b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them.

c. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This individuai shall be responsible for providing positive control over the activities within the area and shall perform j periodic radiation surveillance at the frequency i f specified by the facility health physicist in l l

the Radiation Work Permit.

l 2. The requirements of 6.11.A.1 above, shall also apply l 1 to each high radiation area in which the intensity of l l

radiation is greater than 1000 mrem /hr. In addition, l J

locked doors shall be provided to prevent unauthorized

entry into such areas and the keys shall be maintained e

under the administrative control of the Shift Sup::d::: , ()

on duty and/or the Radiological and Environmental l Services Sup :lnt:nd:nt.,\ Manager i

• Radiation Protection personnel shall be exempt from the RWP issuance j requirement during the performance of their assigned radiation i protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.

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Amendment No. 22r37r38; 256

JAFNPP 6.12 INDUSTRIAL SECURITY PROGRAM ,

(A) An industrial security program shall be maintained throughout the life of the plant in '

accordance with the_pmyisions of tha Pisant Raciwity Plan / awn ~ual review of the Pliiit macurity Plan shall be performed by the Plant Operating Review Committee a_ad_tha-Safety Review Committee.)

6.13 . EMERGENCY PLAN THIS SECTION PURPOSELY BLANK f

6.14 FIRE PROTECTION PROGRAM (6.1 'A An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified licensee personnel or an outside fire

+-- protection firm.

B An inspection and audit by an outside qualified fire consultant shall be performed at intervals no greater than 3 years.

i Amendment No. 07,01 258 ,

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