ML20207K133

Proposed Tech Specs Changing Qualifications for Operations Mgt & Incorporating Generic Titles to Eliminate Need to Develop Amend Request When Corresponding plant-specific Titles Are Changed

ML20207K133
Person / Time
Site:	Beaver Valley
Issue date:	03/03/1999
From:	DUQUESNE LIGHT CO.
To:
Shared Package
ML20207K124	List: L-99-005, Application for Amends to Licenses DPR-66 & NPF-73,changing Qualifications for Operations Mgt & Incorporating Generic Titles in TS to Eliminate Need to Develop Amend Request When Corresponding plant-specific Titles Are Changed ML20207K133
References
NUDOCS 9903170058
Download: ML20207K133 (36)

Text

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1 ATTACHMENT A-1 i I

Beaver Valley Power Station, Unit No. 1

. . Proposed License Amendment Request No. 259 The following is a list of the affected pages:

Affected Pages: 6-1 6-3 6-5 6-6 6-23 6-24 l

9903170058 990303' PDR ADOCK 05000334 p PDR

DPR-66 ADMINISTRATIVE CONTROLS 6,.1 RESPONSIBILITY 6.1.1 The Ocncral Ma ag ,  ! car Opcration shall be I responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.

6.2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS Onsite and Offsite organizations shall be established for facility operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.

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 positi .s . 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. . The e re- shall tc duc eented in the I'C AR . f #584.T )uircacnts pied maugtt ggl

b. The Ocneral Managcr, Nucicar Operatic _) shall be l

responsible for overall-w*it safe operationknd shall have control over those onsite activities necessary for safe operation and maintenance.cf the plant.

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c. The Scnier "i_sfs c$oPrecif. den}. ,9/C0t_.1ccrONo Mu_ ?cucr 5tA.

Division shall I have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant toensurenuclearsafetybWaNe fe $ f*ftC hm,

d. The train the operating staff and those who carry indiv.4dualswho[hycica out health e and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence From operating pressures.

BEAVER VALLEY - UNIT 1 6-1 Amendment No..pyt-Yt0fefed V&tds )

'Ittachm:nt A-1 Bsavar Valley Powsr Station, Unit No. 1 License Amendment Riauest No. 259

, INSERT 1

' These requirements, including the plant-specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications shall be documented in the Unit 2 UFSAR. The correlation between the positions described in . these Technical Specifications and the plant-specific titles are documented in the Unit 2 UFSAR, Table 13.1-2.

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. - ((PR-6 6 q

ADMINISTRATIVE CONTROLS '

t UNIT STAFF (Continued)

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

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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.

lad wa v Any deviationgI rom the bove guidelines shall be authorized by the 0;ncral Manager, "uclear Oper: tic.7 or predesignated alternate, or higher l levels of management. Authorized deviations to the working '

hour guidelines shall be documented and available for NRC review. .

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BEAVER VALLEY - UNIT 1 6- Amendment No. 494 (frofoSe U)otOc.})

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o l . 'DPR-66 l ADMINISTRATIVE CONTROLS _

6.3 FACILITY STAFF OUALIF_ICATIONS ggg 6.3.1 Each member of the facil y and Radiatio Protection staff shall meet or exceed the minimu qualificat'ons of ANSI N18.1-1971 for comparable positions, except -for the "calth .hy:ic Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and the technical advisory engineering representative who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design and response 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 maintained under the direetic. Of the Nuclcar Training Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.

6.5 DELETED j'

6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a. The Commission shall be notified in accordance with 10 CFR 50.72 and/or a report be submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and

b. Each REPORTABLE EVENT shall be reviewed by the OSC, and results of this review shall be submitted to the ORC.

6.7 SAFETY LIMIT VIOLATION l

6.7.1 The following actions shall be taken in the event a safety i

1 Limit is violated:

a. The facility shall be placed in at least HOT STANDBY within one (1) hour. gg

b. The Safety Limit violation shall be reported to the Commission within one hour and to the -Ocncral ::m..;g c r ,

Nuclear Opcrations and to the ORC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the On-Site Safety Committee (OSC). 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. i BEAVER VALLEY - UNIT 1 6-5 . Amendment No.2:' I (ftofoSPcl loo (NW j l

.'. $ttacht:nt A-1 BSnvar Vollsy Powar Station, Unit No. 1 License Amendment Recuest No. 259

. INSERT A

" .....in lieu of license requirements for the operations manager, the supervisor (assistant operations manager, Unit 1) between the operations manager and the licensed operators shall hold a current i Senior Reactor Operator license, .....

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'DPR-66 ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION (Continued) ga gf i

'd . The Safety Limit Violation Report shall b submitted to the Commission, the ORC and the Generel .eneger, him Operations-within 30 days of the violation.

6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978.

b. Refueling operations.

c. Surveillance and test activities of safety related equipment.

d. Not used.

e. Not used.

f. Fire Protection Program implementation.

g. PROCESS CONTROL PROGRAM implementation.

h. OFFSITE DOSE CALCULATION MANUAL implementation.

6.8.2 Deleted 6.8.3 Deleted 6.8.4 A Post-Accident monitoring program shall be established, implemented, and maintained:

A program which will provide the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples following an accident. The program shall include the following:

(1) Training of personnel, (ii) Procedures for sampling and analysis, and (iii) Provisions for maintenance of sampling and analysis equipment.

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l BEAVER VALLEY - UNIT 1 6-6 Amendment No. :::

Yt0pCSch h)0tk Hh, k

., DPit-66 ADMINISTRATIVE CONTROLS l

6.12 HIGH RADIATION AREA 6'.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.1601 of 10 CFR 20, each high radiation area in which l the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall issuance of a Radiological Work Permit g). controlled by requiring or nadi:1cgicc1 7.ccco:- !

Control Fernit. 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. ,

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b. A radiation monitoring device which continuously integrates j the radiation dose rate in the area and alarms when a l preset integrated dose is received. Entry into such areas I 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 l

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who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and (

shall perform periodic radiation surveillance at the I frequency specified by a f acility hcal"i physics supervisor in the Radiological Work Permit, crfRadiclogical?.cccca Contrcl Pernit. gg. gg 4 6.12.2 The requirements of 6.12.1, above, also apply to each high radiation area i.n which the intensity of radiation is greater than  !

1000 mrem /hr. In addition, locked doors shall be provided to j prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift Supervisor l on duty and/or a facility hccith phy:::: supervisor.

ko),he$ f 4YtS htko $$1 0WeC '1N1 l J

(1) ::ccith J

physica personnel, or personnel escorted by T..calth l physics personnel in accordance with approved emergency procedures, shall be exempt from the RWP issuance requirement during the performance of their radiation protection duties, l

provided they comply with approved radiation protection l procedures for entry into high radiation areas.

i BEAVER VALLEY - UNIT 1 6-f3 Amendment No. 09-Yt*f959efMl0th.

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DPR-66 ADMINISTRATIVE CONTROLS 6.13 ,

PROCESS CONTROL PROGRAM (PCP)

Changes to the PCP:

a.

Shall be documented and records of reviews performed shall be retained in accordance with the applicable record retention provision of the quality assurance program description referenced in the Updated Final Safety Analysis Report. This documentation shall contain:

1) Sufficient information to support the change together with the appropriate analyses or evaluations I justifying the change (s) and

2) A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements cf Federal, State, or other applicable regulations.

b. Shall become effective after review and acceptance by the OSC and the approval of the Omneial Manager Nucles.

Operstions,- pecdesignated alternate or a predesignatedi Manager assigned toin whom the censral writing the Manager Nucle ^rr Operetions has for review and approval of specific subjects. responsibility /

6.14 plo d e4 e op v OFFSITE DOSE CALCULATION MANUAL (ODCM) ' v Changes to the ODCM.

a. Shall be documented and records of reviews performed shall be retained in accordance with the applicable record retention provision of the quality assurance program description referenced in the Updated Final Safety Analysis Report. This documentation shall contain:

1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and

2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact  ;

the accuracy or reliability of effluent, dose, or setpoint calculations.

b. Shall become effective af ter review and acceptance by the OSC and the approval of the General Meneger Nucluat Opc rat io ns ," predesignated alternate or a predesignated Manager to whom the-Gener&l Meneger Nuclust GyetaL2voa has f

plQA Mannyte BEAVER VALI EY - UNIT 1 6-p4 Amendment No.2:~

(ft0f0$CW &Y0tha'ap b

ATTACHMENT A-2 Beaver Valley Power Station, Unit No. 2 Proposed License Amendment Request No. 131 The following is a list of the affected pages:

Affected Pages: 6-1 3-2 6-6 6-7 6-22 6-24 6-25 l I

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0PF-73 .

6.0 ADMINISTRATIVE CONTROLS -

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6.1 RESPONSIBILITY I plod manage 1

6.1.1 The Ocncral Manager, "uclear Opcration s-- shall be I responsible for overall facility operation and shall delegate in

' writing the succession to this responsibility during his absence. l j

l 6.2 ORGANIZATION l 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS I i Onsite and offsite organizations shall be established for facility operation and corporate management, respectively. The onsite and '

offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.

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 i and updated, as appropriate, in the form of organization charts, I functional descriptions of departmental responsibilities and I relationships, and job descriptions for key personnel positions, or in equivalent forms of Thcsc requiremenbs- l shall be documented in the TCAR.documentation. h A/SE M / I

b. The 0 ncr: 1. Manager, plat n+An nogy fYh

_uclear Operatienc shall be responsible for overall unit safe operation and shall have control over those I

onsite activities necessary for safe operation and maintenance.

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c. The ccnicr pice$1U l cot)3& de crh Precident,  % ed Nuclear Pcuer Divicicn shall have l corporate responsibility for overall plant nuclear safety and shall .take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

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d. The individuals who train the operating staff and those who carry out hccith paycloe- and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

6.2.2 UNIT STAFF The unit ory. nization shall be subject to the following:

a. Each ' duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

b. At least one licensed Operator shall be in the control room when l fuel is in the reactor.

BEAVER VALLEY - UNIT 2 6- Amendment No.94-(hf0f05e)1b0chls p)

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., Attachm:nt A-2 Bsavsr Vallcy Pownr Station, Unit No. 2

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License Amendment Reauest No. 131 '

i INSERT 1 l

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These requirements, including the plant-specific titles of those l l personnel fulfilling the responsibilities of the positions delineated  !

in these Technical Specifications shall be documented in the Unit 2 I UFSAR. The correlation between the positions described in these Technical Specifications and the plant-specific titles are documented in the Unit 2 UFSAR, Table 13.1-2.

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PF-73 ADMINISTRATIVE-CONTROLS UNIT STAFF (Continued)

c. At least two licensed Operators shall be in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.

d. An individual qualified in radiation protection procedures shall be onsite when fuel is in the reactor.

e. All CORE ALTERATIONS after the initial fuel loading shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

f. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions; senior reactor operators, reactor operators, radiation control technicians, auxiliary operators, meter and control repairman, and all personnel actually performing work on j safety related equipment.

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 plant j 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 l not for the entire staff on a shift.

Any deviation from the above(/ guidelines 194 be shall waMget authorized the cener:1 Manager, Welser Operations or predesignat.e ,

alternate, or higher levels of management. Authorized deviations at the working hour guidelines shall be documented and available for NRC review.

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BEAVER VALLEY - UNIT 2 6-2 Amendment No.v, a (Next pace is 6-5) l Utofosh v)otdig) i

'. ' NPF-73 ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF OUALIFICATIONS g g y /)

' 6.3.'1 Each member of the facil ty and Radiatio Protection staff shall meet or exceed'the minimum qualification of ANSI N18.1-1971 for comparable positions, except the !!;alth Physic; !'anager - who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and the technical advisory engineering representative who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design and response analysis of the plant for tranEients and accidents.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the dircction of-the !!ucicar l l

Training I'anager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.

6.5 DELETED l

6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a.

The Commission shall be notified in accordance with 10 CFR 50.72 and/or a report be submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and

b. Each REPORTABLE EVENT shall be reviewed by the OSC, and the results of this review shall be submitted to the ORC.

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a. The facility shall be placed in at least HOT STANDBY vithin one (1) hour.

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b. The Safety Limit violation shall be eported to the Commission within one hour. The Safety Limit violation shall be reported to the General Laager, Nucicar l Operations and to the ORC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the On-Site Safety Committee (OSC). This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the  !

violation upon facility components, systems or structures, l and (3) corrective action taken to prevent recurrence. l BEAVER VALLEY - UNIT 2 6-6 Amendment No.27 I Y/&f)*Ced LOctYo ,

+ AttachmLnt A-2 B3 vsr Valley Power Stction, Unit No. 2  ;

License Amendment Recuest No. 131

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, INSERT A

" .....in lieu of license requirements for the operations manager, the supervisor (assistant operations manager, Unit 2) between the i operations manager and the licensed operators shall hold a current l Senior Reactor Operator license, .....

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'NPF-73 '

ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION (Continuedi gg g

d. The Safety Limit Violation Report shall b submitted to the Commission, the ORC and the Oer.aral .ar.;gcr, Nucicar-Operatdens- within 30 days of the violation.

6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented, and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix "A" of I

i Regulatory Guide 1.33, Revision 2, February 1978. l

b. Refueling operations.

c. Surveillance and test activities of safety related equipment.

d. Not used.

e. Not used.

f. Fire Protection Program implementation.

g. PROCESS CONTROL PROGRAM implementation.

h. OFFSITE DOSE CALCULATION MANUAL implementation.

6.8.2 Deleted 6.8.3 Deleted 6.8.4 A Post-Accident monitoring program shall be established, implemented, and maintained. The program will provide the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples following an accident. The program shall include the following:

(i) Training of personnel, (ii) Procedures for sampling and analysis, and (iii) Provisions for maintenance of sampling and analysis equipment.

BEAVER VALLEY - UNIT 2 6-7 Amendment No.C' (Next page is 6-14) l (ff 0 fog h 0l0 ! t

.' . i NPF-73 ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued) issuance of a Radiological Work PermitW Or Radiological Access s v.. m v. . - -.

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 1 the radiation dose rate in the area. j i

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 l been made knowledgeable of them.

c. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the 3 frequencyspecifiedbyafacilityhealjhphysicssupervisor in the Radiological Work Permit. cr gRadiclogical Access Ocatrol ;'ersit.

gg gy 6.12.2 The requirements of 6.12.1, above, also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem /hr. In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift Supervisor on duty I and/or a facility hccith physics supervisor.

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Mok e@hysics personnel, or personnel escorted by ..;;1th (1)  ::ealth physics personnel in accordance with approved emergency I

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

BEAVER VALLEY - UNIT 2 6-22 Amendment No. ?

(Next pagg is 6-24) l (Proposed ukd y

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NPF-73 ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (rtgg1 i

I changes to the PCP:

a. Shall be documented and records of reviews performed shall be retained in Lccordance with the applicable record l

retention provision of the quality assurance program l

description included in the Updated Final Safety Analysis Report. This documentation shall contain:

1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and l 2) A determination that the change will maintain the 1 l overall conformance of the solidified waste product to {

existing requirements of Federal, State, or other j l applicable regulations.

l l b. Shall become effective after review and acceptance by the i

OSC and the approval of the C ncr:1 Managcr Nuclear

,Operaticns, predesignated alternate or a predesignatedN Manager to whom the senerel Managar Nucicar Operations has assigned in writing the responsibility & for review snd .

I approval of specific subjects.

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BEAVER VALLEY - UNIT 2 6-f4 , Amendment No.07 (fref03W LOO /Ning)

l NPF-73 ADMINISTRATIVE CONTROLS

'6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM)

Changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained in accordance with the applicable record retention provision of the quality assurance program description included in the Updated Final Safety Analysis Report. This documentation shall contain:

1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and

2) A determinati'on that the change will caintain the level  ;

of radioactive effluent control required by 10 CFR f 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I '

to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b. Shall become effective after review and acceptance by the OSC and the approval of the Ocncral ' Manager Nuciccr

-eperations, predesignated alternate or a predesignatedT Manager to whom the -Genere-1 Mancgcr Nucic r Opcrctienc has assigned in writing the responsibilityffor review l

approval of specific subjects. andj  !

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c. Shall be submitted to the Commission in the form of a i complete, legible copy of the entire ODCM as a part of or  !

concurrent with the Annual Radioactive Effluent. Release Report for the period of the report in which any change to ,

the ODCM 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, and shall l indicate the date (e.g., month / year) the change was implemented.

6 16 Moved to the PROCESS. CONTROL PROGRAM.

6.17 CONTAINMENT LEAKAGE RATE TESTING PROGRAM A program shall be established to implement the leakage rate testiner of the containment as required by 10 CFR 50.54 (o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptionsW .

This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program," dated September 1995.

(1) Exemptions to Appendix J of 10 CFR 50, as stated in the operating license.

BEAVER VALLEY - UNIT 2 6 25 Amendment No.07 (ff0)00S &d&I'

ATTACHMENT B Beaver Valley Power Station, Unit Nos. 1 and 2 License Amendment Request Nos. 259 and 131 REVISION OF MINIMUM QUALIFICATIONS FOR OPERATIONS MANAGEMENT

& PERSONNEL TITLES A. DESCRIPTION OF AMENDMENT REQUEST The proposed amendment changes the qualifications for operations management specified in the Technical Specifications for the Beaver Valley Power Station (BVPS) Units 1 and 2.

The requirement that the operations manager hold an SRO License at the time of appointment, as required by ANSI N18.1-1971, will be changed in the Technical Specifications to require the l essistant operations managers, one for each Unit, to hold an SRO License on their assigned Unit. The Technical Specifications will not then require the operations manager to hold a License.

This is more restrictive, in that the operations manager could hold a license on only one unit. With this change there will be an individual manager in charge at each Unit who will be required to have an SRO license.

The UFSAR will be changed to require the operations manager to hold or have held an SRO License rather than presently hold an SRO License. The UFSAR will require the same as the Technical Specifications, that the assistant operations managers hold an SRO License on the Unit to which they are assigned.

In addition, the proposed amendment substitutes generic personnel titles for plant-specific personnel titles. The correlation between generic titles and plant-specific titles will be provided in the Unit 2 UFSAR.

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B. DESIGN BASES The BVPS Technical Specifications, in Section 6.3.1 specifies that each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions. ANSI N18.1-1971, in Section 4.2.2, Operations Manager, specifies at the time of initial core loading or  ;

appointment to the active position the operations manager shall '

hold a Senior Reactor Operators (SRO) License.  ;

i ISTS specifies, in Section 5.2.2.f, that the "[ Operations Manager  ;

or Assistant Operations Manager)" shall hold an SRO license.

The BVPS Technical Specifications specify the responsibilities of I particular personnel by BVPS unique titles. TSTF-65, Rev 1 provides generic titles that can be used in lieu of plant- I specific titles. In this amendment the generic titles are substituted for plant-specific titles.

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' ATTACHMENT B, continutd l Proponed Licnnsa Am ndmnnt Rnquest Nos. 259 and 131 l Pcgs 2 I

l C. JUSTIFICATION

, 1 At BVPS the plant manager has overall responsibility for the plant. Reporting to the plant manager is the operations manager '

who has responsibility for the operations of both units and as j such has broad responsibilities for direction of operational l activities, their planning, as well as recruitment and assignment i of licensed operators. At BVPS there are two supervisors l l [ assistant operations managers], one for each unit, who are  !

intermediate in-line managers between the reactor operators and the General Manager, Nuclear Operations. Each one of these supervisors is responsible for the direct oversight of the licensed reactor operators at one of the BVPS units and is therefore required to hold a current SRO License for the unit  ;

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As a result of the proposed changes in this LAR, the Beaver  !

Valley assistant operations manager's qualifications will meet l the intent of ANSI-18.1-1971. The provision for the assistant operations managers to hold an SRO License is consistent with ,

ISTS that states, in Section 5.2.2, "The [ Operations Manager or '

Assistant Operations Manager) shall hold an SRO License." The I assistant operations managers, one for each unit, will each be  !

required, in the Technical Specifications, to hold an SRO l License. This is more than previously required, in the Technical l Specifications, where only the operations manager was required to meet the ANSI Standard [which requires the operations manager hold an SRO License at the time of appointment). The NRC only i permits an individual to hold an SRO License on one of the BV units at a time. Thus, this change introduces more restrictive license requirements for operations management. In addition, the proposed changes to the UFSAR [ Attachment C of the LLR) will  !

require the operations manager to hold or have held an SRO  !

License.  !

i Substitution of 'teneric titles avoids the need to modify the i Technical Specifications when plant-specific personnel titles are l changed. l l

D. SAFETY ANALYSIS j Since the supervisors between the operations manager and the licensed reactor operators are responsible for the direct  !

oversight of the licensed reactor operators at each unit it is I these individuals, one per unit, who are required to hold a  ;

current SRO License for the unit managed. i i

The substitution of generic titles for plant-specific titles helps minimize the need for Technical Specification changes when f plant-specific titles are changed.

B-2 I

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• ATTACHMENT B, continund Proposed Licensa Amsndmant Rcquest Nos. 259 and 131 Pr.gn 3

, , These are changes that do not affect the operation of the plant; therefore, these changes have been determined to be safe and will l not impact the safety of the plant. l E. NO SIGNIFICANT HAZARDS EVALUATION The no significant hazard considerations involved with the 3 proposed amendment have been evaluated, focusing on the three l standards set forth in 10 CFR 50.92(c) as quoted below:

The commiss, ion may make a final determination, pursuant to the procedures in paragraph 50.91, that a proposed amendment to an operating license for' a facility licensed under paragraph 50.21(b) or paragraph 50.22 or for a testing facility involves no significant hazards consideration, if operation of the facility in accordance ' with the proposed amendment would not:

(1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or 1

(3) Involve a significant reduction in a margin of safety.

The following evaluation is provided for the no significant hazards consideration standards.

1. Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?

The proposed changes are administrative in nature. The revised requirements for who must hold a current senior reactor operator (SRO) License does not involve any cnange to the configuration or method of operation of any plant equipment that is used to mitigate the consequences of an accident nor alter the conditions or assumptions in any of the Updated Final Safety Analysis Report [UFSAR] accident analyses. The requirement that the operations manager hold or have held an SRO License is included in the revised Position Qualifications in the Unit 2 UFSAR, Table 13.1-2, sheet 30 of 35. The title changes are being made, consistent with TSTF-65, Rev 1 and help avoid the need for future Technical Specification changes. Therefore, it can be concluded that the proposed changes do not involve any increase in the probability or consequences of an accident previously evaluated.

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• TTACHMENT 3, continund Propo:2ed License Amendmsnt Request Nos. 259 and 131 Pago 4 j

1. l

. .2. Does the change create the possibility of a new or different l kind of accident from any accident previously evaluated? j l

No new failure modes are defined for any plant system or j component important to safety nor has any new limiting failure been identified as a result of the proposed changes.

Therefore, it can be concluded that the proposed change does not create the possibility of a new or different kind of accident from those previously evaluated.

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3. Does the change involve a significant reduction in a margin of safety?

The proposed changes are administrative in nature. One of the proposed changes requires that the manager who directly supervises the licensed operators at each unit be the holder of a current SRO license. The other change modifies personnel titles. Therefore, it can be concluded that the j proposed changes do not involve any reduction in a margin of i safety. i F. NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION l

Based on the considerations expressed above, it is concluded that l the activities associated with this license amendment request j satisfy the requirements of 10 CFR 50.92(c) and, accordingly, a {

l no significant hazards consideration finding is justified.

G. ENVIRONMENTAL CONSIDERATION l This license amendment request changes to the qualifications of operations management and revises some personnel titles. It has i been determined that this license amendment request involves no I

significant increase in the amounts, and no significant change in the types of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. This license amendment request does not change requirements with respect to installation or use of any facility component located within the restricted area or change an inspection or surveillance requirement; however, the category of this licensing action does not individually or cumulatively have a significant effect on the human environment.

Accordingly, this license amendment request meets the eligibility criteria for categorical exclusion set forth in 10 CFR I

51. 22 (c) (9) . Pursuant to 10 CFR 51.22(b) no environmental impact l statement or environmental assessment need be prepared in l connection with the issuance of this license amendment request.

H. UFSAR CHANGES  !

UFSAR changes are required. See Attachment C.

l B-4 l

i ATTACHMENT C-1 Beaver Valley Power Station, Unit No. 1 Proposed License Amendment Request No. 259 Applicable UFSAR Changes l

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m I BVPS-1-UPDATED FSAR Rev. 0 (1/82) accordance with- the' AEC regulatory position outlined in Safety

. Guide 6. l l

The electrical power loads for engineered safety features are separated into redundant load groups fed from separate buses such  !

that loss. of one group- will not prevent operation of minimum pafety-functions. )

{

The redundant power loads are each connected to buses which may j have power fed from an offsite power source or an onsite power l source (a diesel generator) .

Four 125 v d-c systems, each complete with batteries, chargers, switchgear, and distribution equipment, are provided for engineered safety feattires equipment. These systems are not tied I together.

A standby source of power for one redundant load cannot be automatically paralleled with the standby source of power for 1 the other redundant load.

]

Each redundant 120 a-c engineered safety features load is supplied with power from a separate emergency diesel generator.

Figures 8.5-1, 8.5-2, and 1.2-12 illustrate the physical arrangement . of the diesel generators, emergency switchgear, 1 125 v d-c batteries, battery chargers, 125 v d-c distribution j panels and 120 v a-c vital bus system equipraent. '

l.3.3.7 Control of Combustible Gas Concentrations in Containment Following a Loss-of-Coolant Accident (Safety Guide 7)

Table 14.3-9 lists the parameters used in calculating hydrogen sources. These parameters are identical to those given in' Safety Guide 7. Further discussion of the post DBA hydrogen control  !

system is presented in Section 6.5. An analysis of hydrogen i generation and control is given in Section 14.3.4.4.

1.3.3.8 Safety Guide 8)

Personnel B$ c.e f f as sf Selectign ac.Wsed o*nandthe Training Tie 4me (dSpea sha;tm.s The personnel of the BVPS-1 are selected and trained n conformance with the " Standard for Selection and Trai iny i of Personnel for Nuclear Power Plants," ANSI N18.1-197 O i Conformance with this standard assures that the requirements of the AEC Safety Guide 8 are met in their entirety.  !

The organization of BVPS-1 is described in Section 12.1 The training program for the various job classifications is listed in Section 12.2.

1.3.3.9 Selection of Diesel Generator Set Capacity for Standby Power Supplies (Safety Guide 9) 1.3-36

• l ATTACHMENT C-2 Beaver Valley Power Station, Unit No. 2 Proposed License Amendment Request No. 131 Applicable UFSAR Changes I

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,'- BVPS-2 UFSAR Rev. 1 TABLE 1.8-1 (Cont)

RG No. 1.7, Rev. 2

,' UFSAR Reference Section 6.2.5

• CONTROL OF COMBUSTIBLE GAS CONCENTRATIONS IN CONTAINMENT FOLLOWING A LOSS-OF- [ .

COOLANT ACCIDENT (NOVEMBER 1978)

• The design of the -h ydrogen control system for- Beaver Valley Power Station - Unit 2 follows the guidance of Regulatory Guide 1.7.

RG No. 1.8, Rev'. 1-R UFSAR Reference Sections 12.5, 13.1, 13.2 PERSONNEL SELECTION AND TRAINING (MAY 1977)

Selection and training of Beaver Valley Power Stati -

Unit 2 yersonnel will follow the guidance of this regulator { guidef eXc. as s e H4/ ,4 RG No. 1.9, Rev. 2 m Te~cA A cal sp bdm;,.,.

UFSAR Reference Sections 8.3.1.1.15, 14.2.12.54, 14.2.12.55 SELECTION, DESIGN, AND QUALIFICATION OF DIESEL-GENERATOR UNITS USED AS STANDBY .

(ONSITE) ELECTRIC POWER SYSTEMS AT NUCLEAR POWER PLANTS (DECEMBER 1979) ,

Diesel-generator units used as onsite electric power system's at BVPS-2 have been selected, designed, and qualified following the guidance of this Regulatory Guide with the following alternative and clarifications:

The Class 1E diesel generator units were designed and procured following the guidance of Regulatory Guide 1.9, Rev. 0 (March 1971)- and IEEE St'andard 387-1972. (Revision status at time of design / procurement) l However, the Class 1E diesel generators were manufactured to IEEE Standard t" 387-1977 with the following clarifications: .

1. Section 4.1[8): The BVPS-2 Class 1E diesels are qualified utilizing l the mild environment concept acknowledged by 10CFR50.49(c).

2. Section 4.1[12): The BVPS-2 Class 1E diesels are seismically l qualified in accordance with IEEE Standard 344-1971.

3. Section 5.4: The BVPS-2 riass 1E diesels are qualified utilizing the mild environment concept acknowledged by 10CFR50.49(c).

l l 4. Section 6.3.1: All required tests or analyses have been performed by the manufacturer with the exception of the 3 of 80

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., BVPS-2 UFSAR R;v. 10 l l13.1.2.6 Responsibilities and Qualifications l Responsibilities and minimum qualifications of key individuals in the

. Nuclear Power Division are provided in Table 13.1-2.

l l The line of succession of authorii.y and responsibility for overall l operation in the event of unexpected contingencies of a temporary l nature is set forth as follows:

1. Division Vice President, Nuclear Operations Group & Plant Manager (p/s.g/~M4HAgd.a')

2. General Manager, Nuclear Operations Unit (ofte*dthdf Ne

3. Technical Assistant to Vice President, Nuclear Operations Group & Plant Manager i

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7;% of key ;2hdads, when Swk}- ),*c}&, ag Fot/odJ y /ki) yn,. ;e. 1iffs., a p m.dke rb, hm tk 7&c4 >ub/ spec'rf/cdks .

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BVPS-2 UFSAR R2v. 10 TABLE 13.1-2 PERSONNEL RE3PONSIBILITIES AND QUALIFICATIONS f $f /hl NY 49tf teht*. $ 1CtF,ggg Poeition l President, Generation Group & Chief Nuclear Officer" 3 lSeniorVicePresident, Nuclear Services Group 4 lDivisionVicePresident, Operations Support Group 5 lDivisionVicePresident, Nuclea Operations Group 6

& Plant Manager (g/d[M4A 4 lAssistantVicePresident, Nuclear Human Resources Unit 7

)

l Manager,QualityServicesUnit 8 l Manager,NuclearEngineering '

9 l Director, Information Services 10 l [ b , Nuclear Safety & Licensing 11 l Manager, System &PerformanceEngineering 12 I

l Director,SystemEngineering 13 )

l Director,PerformanceEngineering 14 l Supervisor,ReactorEngineering 15 lShiftTechnicalAdvisor 16 l Manager,ProcedureUpgrade 17 lGeneralManager,NuclearSupportUnit 18 l Manager,OutageManagement 19 l Supervisor, Refueling 20 Manager, Nuclear Security 21 Technical Assistant to the Division Vice President, 22 Nuclear Operations Group & Plant Manager l General Manager, Maintenant.q Programs Unit 23 l Manager,WorkManagement 24 lDirectorInstrument&ControlsMaintenance 25 1 of 35

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. ,' . BVPS-2 UFSAR R3v. 10 TABLE 13.1-2 (Cont)

Posit ion h Director, Maintenance Support 26 l l

Manager, Nuclear Construction 27 l Manager, Health Physics [ M i ki b p M C, e , % ,,a ,a) 28 l Manager, Chemistry 29 l )

General Manager, Nuclear Operations Unit hpMMeg s+fdddfd 30 l tia NucglarShiftSupervisor-Unit 1t, Rauf I C&do.s (asukhd o@ia,r 31 myk&-

l l Assistant Nuclear Shift Supervisor - Unit 1 32 l

$9 , dness X CB S L (ast 5l d ojea W S ,s W a y s* tlk h Nucl%ar Shift Supervisor - Unit 2 l

33 l l

Assistant Nuclear Shift Supervisor - Unit 2 34 l Coordinator, Onsite Safety Conunittee 35 l l

2 of 35

BVPS-2 UFSAR R v. 10 TABLE 13.1-2 (Cont) pfkYCMf4f klC l POSITION: PRESIDENT GENERATION GROUP AND CHIEF NUCLEAR OFFICER l

POSITION RESPONSIBILITIES:

Reports to the Duquesne Light Company President and Ch- f Executive Officer. The President Generation Group and Chief Nuclear Officer has the responsibility for the overall operation of the Beaver Valley Power Station.

Directs the Nuclear Services Group, Nuclear Operations Support Group, Nuclear Operations Group and all units or departments which support the plant operations.

POSITION QUALIFICATIONS:

A Bachelor of Science Degree in Engineering or Physical Sciences Ten (10) years experience in design, operation, maintenance, testing, or licensing of nuclear power plants, at least five (5) years of which shall have been in a position of line responsibility.

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BVPS-2 UFSAR Rsv. 10 TABLE 13.1-2 (Cont)

POSITION: DIVISION VICE PRESIDENT, NUCLEAR OPERATIONS GROUP & PLANT l MANAGER h/a7Mada h POSITION RESPONSIBILITIES:

Reports to the President, Generation Group and Chief Nuclear Officer.

The Division Vice President, Nuclear Operations Group & Plant Manager is responsible for operations activities, maintenance programs, chemistry activities, onsite safety, health physics and nuclear j construction activities.

POSITION QUALIFICATIONS:

A Bachelor of Science Degree in Science or Engineering or as delineated in ANSI N18.1-1971, (4.2.1).

Fifteen (15) years experience in electrical generating business or power plant operation of.which ten (10) years is nuclear experience.

Eight (8) years supervisory or management experience in position responsible for operation of support of nuclear power generation.

6 of 35

• -[ ' BVPS-2 UFSAR R2v. 10 TABLE 13.1-2 (Cont) I l

POSITION: MANAGER, HEALTH PHYSICS ( M / p Nsf dg e POSITION RESPONSIBILITIES:

Reports to the Division Vice President, Nuclear Operations Group & l l Plant Manager. The Manager, Health Physics is responsible for the providing .adiological engineering & health l l

following activities:

services and radiological control coverage, implementation of ALARA analysis, protiding direction and support for all radiological waste shipping, rad waste management, maintaining the dosimetry and respiratory protection program, environmental services, and l implementing tFe industrial safety program. This manager also serves I as Radiation Protection Manager specified in NRC Regulatory Guide 8.8.

I POSITION QUALIFIC7.* IONS:

1 A Bachelor of Science Degree in Science or Engineering. I Eight (8) years or more professional experience in applied health physics, including at least six (6) years in radiation protection supervision at a nuclear power plant.

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BVPS-2 UFSAR R3v. 10 l

TABLE 13.1-2 (Cont)

POSITIt: GENERAL MANAGER, NUCLEAR OPERATIONS UNIT (o p M J **MM8 [

POSITION RESPONSIBILITIES:

Reports to the Division Vice President, Nuclear Operations Group &

Plant Manager. The General Manager, Nuclear Operations Unit is responsible for all operations activities at Beaver Valley Power Station.

POSITION QUALIFICATIONS:

A Bachelor of Science Degree in Engineering or related science, or equivalent.

Ten (10) years or more technical or supervisory experience of which at least 5 years are nuclear related.

oc ku held a,., w af r;rr .t.gjaj Holds Aa Senior Reactor Operator NRC License at .3 d

facility.

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• • ' Attschm:nt C Banysr Vallcy Powar Station, Unit No. 2 License Amendment Reauest No. 131

, INSERT 2 Table 13.1-2 (cont)

POSITION: MANAGER, UNIT 1 OPERATIONS (assistant operations manager, Unit 1)

POSITION RESPONSIBILITIES:

Reports to the General Manager, Nuclear Operations Unit. The Manager, Unit 1 Operations is responsible for all operations activities at Beaver Valley Power Station Unit 1.

POSITION QUALIFICATIONS:

A Bachelcr of Science Degree _in Engineering or related science, or equivalent. l (8) years or more technical or supervisory experience of which at least (3) years are nuclear related.

Holds a Senior Reactor Operator NRC License at Beaver Valley Power Station Unit 1.

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• w "Attechmant C Bsavar Valley Powar StOtion, Unit No. 2 License Amendment Recruest No. 131

. INSERT 3 Table 13.1-2 (Cont)

POSITION: MANAGER, UNIT 2 OPERATIONS (assistant operations manager, Unit 2) )

POSITION RESPONSIBILITIES:

Reports to the General Manager, Nuclear Operations Unit. The Manager, Unit 2 Operations is responsible for all operations ' activities at Beaver Valley Power )

Station Unit 2.

POSITION QUALIFICATIONS:

A Bachelor of Science. Degree in Engineering or related science, or equivalent.

(8) years or more technical or supervisory experience of which at least (3) years are nuclear related.

Holds a Senior Reactor Operator NRC License at Beaver Valley Power Station Unit 2.

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