ML20082C513

Amends 159 & 38 to Licenses DPR-66 & NPF-73,respectively, Revising Tech Specs by Replacing Previous Titles W/New Titles

ML20082C513
Person / Time
Site:	Beaver Valley
Issue date:	07/11/1991
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Duquesne Light Co, Ohio Edison Co, Pennsylvania Power Co
Shared Package
ML20082C516	List: ML20082C513 ML20082C519
References
DPR-66-A-159, NPF-73-A-038 NUDOCS 9107190160
Download: ML20082C513 (26)

Text

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f# "%q Qf)f 'n l!O UNITED STATES 1.d J c[i NUCLEAR REGULATORY COMMISSION

- WASHINGTON. O.C. 20666 o

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i DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET ff0. 50-334 BEAVER VALLEY POWER STATION, UNIT'ti0. 1 AMEt:DMENT TO FACILITY OPEPATING LICENSE Amendment No.159 License No. DPR-66 1.

The. Nuclear Pegulatory Connission (the Connission) has found that:

A.

The ' application' for amendment by Duquesne Light Company, et.- al. (the licensee) dated April-4,-1990 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and:the Connission's rules and regulations set forth in 10 CFR Chapter I;.

-B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public,- and (ii) that such activities will be conducted in compliance with the Connission'.s regulations; y

D.-

The; issuance of this-amendment will not be inimical to the connon defense and security or to the health and safety of the public; and' E. -- -The-issuance of this amendment is in accordance with 10 CFR Part 51 of-the.Connission's regulations and all applicable requirements have been satisfied.-

9107190160 910711 PDR ADOCK 05000334 P

PDR

2 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Fecility Operating License No. DPR-66 is hereby amended to read as follows:

-( 2 ) Technical Specifications The Techn' cal Specifications contained in Appendix A, as revised through Amendment No.159, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance, to be implenented within 60 days of issuance.

FOR Tl!E NUCLEAR REGULATORY COPMISSION

b. b lohn F. Stolz, Director Project Directorate I-4 Division of Reactor Projects - 1/11 Office of Huclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: July 11,1991

ATTACWENT_ TO LICENSE,AD,EpDMEN,T,p0.,159 FAClllTY OPERATING LICENSE NO. OPR-66 DOCKET NO. E0,3,3,4 Replace the following pages of Appendix A, Teci:,iical Specifications, with the enclosed pages as indicated. The revised pages are identified by arcendment nuriber and contain vertical lines indicating the areas of change.

Remove Insert 6-1 6-1 6-3 6-3 6-5 6-5 6-6 6-6 6-7 6-7 6-12 6-12 6-13 6-13 6-31 6-31 i

__.._--.___.m_-______.m_.

ADMINISTRATIVE CONTROLS l

'6.1 RESPONSIBILITY 6.1.1 The General Manager Nuclear Operations shall be responsible l 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 positions.

These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.

These requirements shall be documented in the FSAR.

b.

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

c.

The Vice President Nucleer Group shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure accf.ptable performance of the staff in operating, raintaining, and providing technical support to the

-plant to ensure nuclear safety, d.

The-individuals who train the operating staff and those who carry out health physics 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. 74, 110, 131, 159

AD'MINISTRATIVE CONTROIS 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 General Manager Nuclear Operations or predesignated alternate, or l higher levels of management.

Authorized deviations to the working hour guidelines shall be documented and available for NRC review.

BEAVER VALLEY - UNIT 1 6-3 Amendment No. 79, 110, 131, 159

ADMINISTRATIVE CONTROLS l

6.3 FACILITY STAFF OUALIFICATIONS 6.3.1 Each member of the facility and radiation protection staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 1

for comparable positions, except for the Health Physics Manager who l I

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 direction of the Nuclear Training Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A"

of 10 CFR part 55.

6.5 REVIEW AND AUDIT 6.5.1 ONSITE SAFETY COMMITTEE (OSC)

FUNCTION 6.5.1.1 The OSC shall function to advise the General Manager Nuclear Operations on all matters related to nuclear safety and shall provide review capability in the areas of:

a.

nuclear power plant operations b.

radiological safety c.

maintenance d.

nuclear engineering e.

nuclear power plant testing f.

technical advisory engineering g.

chemistry h.

quality control 1.

instrumentation and control COMPOSITION 6.5.1.2 The Onsite Safety Committee Supervisor is the OSC Chairman I and shall appoint all members of the OSC.

The membership shall consist of a

minimum of one individual from each of the areas designated in 6.5.1.1.

OSC renbers and alternates shall meet or exceed the minimum qualifications of ANSI N18.1-1971 Section 4.4 for comparable positions.

The nuclear power plant operations individual chall meet the qualifications of Section 4.2.2 and the maintenance individual shall meet the qualifications of Section 4.2.3.

BEAVER VALLEY - UNIT 1 6-5 Amendment No. 67, 110, 136,155, b

ADMINISTRATIVE CONTROLS ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the 1

OSC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in OSC activities at any one time.

MEETING FREQUENCY 6.5.1~.4 The OSC shall meet at least once per calendar month and as convened by the OSC Chairman or his designated alternate.

QUORUM 6.5.1.5 A~

quorum of the OSC shall consist of the Chairman or his designated alternate and at least one half of the members including alternates.

RESPONSIBILITIRE 6.5.1.6 The OSC shall be responsible for:

a.

Review of 1) all procedures required by Specification 6.8 and changes of intent

thereto, 2) any other proposed procedures or changes thereto as determined by the General Manger Nuclear Operations 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 including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the General Manager, Nuclear Operations and to the Chairman of the Offsite Review Committee.

f.

Review of all REPORTABLE EVENTS.

g.

Review of facility operations to detect potential safety hazards.

h.

Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Offsite Review Committee.

BEAVER VALLEY UNIT 1 6-6 Amendment No. 84, 110, 131,159

A6MINISTRATIVE CONTROLS i

AMIBORITY 6.5.1.7 The OSC shall:

a.

Recommend to the General Manager Nuclear Operations written l 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.

c.

Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President Nuclear Group and the Offsite Review Committee of disagreement between the OSC and the General Manager Nuclear Operations;

however, the General Manager Nuclear Operaticns shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

RECORDS 6.5.1.8 The OSC shall maintain written minutes of each meeting and copies shall be provided to the General Manager Nuclear Operations and Chairman of the Offsite Review Committee.

6.5.2 OFFSITE REVIEW COMMITTEE (ORQ1 FUNCTION 6.5.2.1 The ORC shall function to provide independent review and audit of designated activities in the areas of:

a.

nuclear power plant operations I

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 BEAVER VALLEY - UNIT 1 6-7 Amendment No. 67, 110, 131, 159

)

_,.. _... _. _ _. ~.. _. _ _ _.,. _ _. _ _ _ _ _. _. -. _. _. _. _ _. - _. _.. _ _

1

'AbMINISTRATIVE CONTROIA 1

SAFETY LIMIT VIOLATION (Continued) c.

A Safety-Limit Violation Report shall be prepared.

The report shall.be reviewod by the On-Site Safety-Committee--(OSC).

This i

report' shall describe (1) applicable circumstances proceeding 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 ORC and the General Manager, Nuclear 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:

i a.

The applicable _

procedures recommended in. Appendix "A"

of Regulatory Guide 1.33, Revision 2, February 1978.

b.

-Refueling operations.-

)

Surveillance.and test. activities of safety related equipment.

c._

d.

Security Plan' implementation.

- e.

Emergency Plan implementation'.

f.

Fire Protection Program implementation.

g.

PROCESS CONTROL PROGRAM' implementation.

- h.

OFFSITE DOSE CALCULATION-MANUAL: implementation.

6.8.2-Each -procedure andiadministrative policy of 6.8.1-above'.and changes nof ; intent-thereto,.shall be' reviewed by the.oSC and' approved.

- by the -General'_ Manager-Nuclear Operations, predesignated-alternate, or-a predesignated Manager-:te whou: the General Manager Nuclear operations has -assigned in writing the responsibility for review and approval-- of specific subjects considered by.the committee,- -as applicable.-

Changes to~ procedures and administrative policies-of 6,8.1 above that

.do-not raceive -OSC-review, such as correcting

- typographical -errors,. reformatting.. procedures:and other changes not-

- affecting the purpose for which the' procedure is performed shall

- receive.an independent' review by a qualified individual and approved-by.a designated: manager or-' director.

4 SEAVER VALLEY - UNIT 1 6 - 12 Amendment No. 66, 110, 120, 131, 159

_.. -. _ _ _ _.... _ _ _ _ ___ _ - _ _..._.. _.._ _. _.__ _ _ __-.. _. _ _ _ ~ _ _.~....._.~. _, _.... _ _

a ADMINISTRATIVE CONTROLS l

6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

a.

The intent of the original procedure is not altered.

b.

The change is approved by two (2) members of the plant management

staff, at least one (1) of whom holds a Senior Reactor Operator's License on the unit affected.

c.

The change is documented, reviewed by the OSC and approved by the General Manager Nuclear Operations,predesignatedj alternate or a

predesignated Manager to whom the General Manager Nuclear Operations has assigned in writing the responsibility for review and approval of specific subjects, within 14 days of implementation.

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:

(i)

Training of personnel, (ii)

Procedures for sampling and analysis, and (iii)

Provisions for maintenance of sampling and analysis equipment.

6.8.5 A

program for monitoring of secondary water chemistry to inhibit steam generator tube degradation shall be implemented.

This program shall be described in the station chemistry manual and shall include:

a.

Identification of a

sampling schedule for the critical parameters and control points for these parameters; b.

Identification of the procedures used to measure the values of the critical parameters; c.

Identification for process sampling points; d.

Procedures for the recording and management of data; e.

Procedures defining corrective actions for off control point chemistry conditions; and f.

A procedure identifying:

1) the authority responsible for the interpretation of the data, and 2) the sequence and timing of administrative events required to initiate corrective action.

l BEAVER VALLEY - UNIT 1 6 - 13 Amendment No. 84,105,110,112,131,159

ADMINISTRATIVE CONTROLS I

6.17 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The General Manger Nuclear Operations delegates the responsibility for the Radiological Environmental Monitoring Program to the Health Physics Manager or his designated alternate.

1 The Health Physics Manager is responsible for administering thol Offsite Radiological Environmental Monitoring Program.

He shall determine that the sampling program is taing implemented as described to verify that the environment is adequately protected under existing procedures.

He shall also have the responsibility for establishing, implementing, maintaining and approving Offsite environmental program sampling, analyses and calibration procedures.

BEAVER VALLEY - UNIT 1 6-31 Amendment No. 66, 110, 131, 159

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NUCLEAR REGULATORY COMMISSION kh WASHINoToN, D C. 20M6 g w.. < f

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DUQUESHE LIGHT COMPANY OH10 EDIS0H COMPANY THE CLEVELAND ELECTRIC ILLUMINATitlG COMPAtlY THE TOLEDO EDISON COMPAHY DOCKET P0. 50-412 BEAVER VALLEY F0WER STATION, UNIT HO. ?

AMENDMENT TO FACILITY OPERATING LICENSE Amendnent No. 38 License No. NPF-73 1.

The !!uclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Duquesne Light Company, et. al. (the licensee) dated April 4,1990 complies wi'h the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that tha activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

1

2 2.

Accordingly, the license is an+nded by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License 110. HPF-73 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 38, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. DLCO shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance, to be implemented within 60 days of issuance.

FOR THE t!PCLEAR REGULATORY COMMISSION Y.

W John F. Stolz, Director Project Directorate I-4 Division of Reactor Projects - 1/11 Office of ttuclear Reactor Pegulation

Attachment:

Changes to the Technical Specifications Date of Issuance: July 11, 1991

ATTACHMENT TO LICENSE AMENDMENT 110.38 FACILITY OPERATING LICENSE NO. DPR-73 DOCKET NO. 50 412 i

ll Replace the following pages of Appendix A, Technical Specifications, with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Pemove Insert 6-1 6-1 6-2 6-2 6-6 6-6 6-7 6-7 6-8 6-8 6-12 6-12 6-13 6-13 6-?4 6-24 pw -

u a

m-.--

mm

.m m

l 1

e-l I

6.0 ADMINISTRATIVE CONTROLS l

6.1 RESPONSIBILITY 6.1.1 The General Manager Nuclear Operations shall be responsible for overall I

facility operation and shall delegate in writing the succession to this respon-sibility during his absence.

3 l

6.2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATIONS Onsite and offsite organizations shall be established for facility 0;,eratian and corporate manage 4ent, 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 e,nd including all operating organization positions.

These relationships shall be documented and updated, as appropriate, in the form of organization c. harts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.

These requirements shall be documented in the FSAR.

b.

The General Manager Nuclear Operations shall be responsible for overall l

unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

c.

The Vice President Nuclear Group shall 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 to ensure nuclear safety.

d.

The individuals who train the' operating staff and those who carry out health physics and quality assurance functions may report to i.he appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

6.2.2 UNIT STAFF The unit organization 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 fuel is in the reactor.

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.

BEAVER VALLEY - UNIT 2 6-1 Amendment No. 7,38

~

ADMINISTPATIVE CONTROLS UNIT STAFF (Continued) d.

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

All CORE ALTERATIONS after the initial fuel loading shall be directly e.

supervised by either a licensed Senior Reactor Operatar or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

f.

Administrative procedurea shall be developed and implermented to limit the working hours of unit staff who perform safety-related functimis; senior reactor operators, reactor operators, radiation contesi tech-nicians, auxiliary operators, meter and control repairman, and all personnel actually performing work on safety related equipment.

The objective shall be to have operating personnel work a 1ormal 8-hour day, 40-hour week while the plant is operatino; lhver, 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 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 haurs in any 48-nour 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 shal! be authorized by the General Manager Nuclear Operations or predesignated alternate, or higher l

levels of management.

Authorized deviations to the working hour guide-lines shall be documented and available for NRC review.

l 6.2.3 INDEPENDENT SAFETY EVALUATION GROUP (ISEG) l FUNCTION l-6.2.3.1 The ISEG shall function to examine unit operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of unit design and operating experience information, including units of simi-lar design, which may indicate areas for improving unit safety.

The ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activities, or other means of improving unit safety to corporate management.

If not otherwise implemented, all recorrunda-tions shall then be made to the Vice President, Nuclear Group, i

BEAVER VALLEY - UNIT 2 6-2 Amendment No. 7,38

TABLE 6.2.1 MINIMUM SHIFT CREW COMPOSITION #

SINGLE UNIT FACILITY LICENSE CATEGORY APPLICABLE H0 DES QUALIFICATIONS 1, 2, 3 and 4 5 and 6 hRO*

2 1**

R0 2

1 Non-licensed Auxiliary Operator 2

1 Shift Technical Advisor 1(a)

None Required

• Includes the Licensed Senior Reactor Operator serving as the Shift Supervia*r.

• • Does not include the Licensed Senior Reactor Operator or Senior Reactor Operatt,r Limited to Fuel Handling, supervising CORE OPERATIONS.

1. Shift crew composition may be one less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action ie. taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.

This provision does not permit any shitt crew position to be unmanned upon shift ch3nge due to an oncoming shift crewman being late or esent.

(a)The Shif t Technical Arivisor (STA) position may be fi' led by the same STA from the BVPb Unit 1, if the individual is qualified for BVPS Unit 2.

BEAVER VALLEY - UNIT 2 6-5

ACHitdil,RATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility and Radiation Protection staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the Health Physics Manager who shall meet or exceed the qualifications l

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 disciplir.e with specific training in plant design and response analysis of the plant for transients and accidents.

6.4 TRAI"ING 6.4.1 A retraining and replacemert training program for the facility staff shall be maintained under the direction of the Nuclear Training Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.

6.5 REVIEW AND AUDIT 6.5.1 ONSITE SAFETY COMMITTEE (OSC)

FUNCTION 6.5.1.1 The OSC shall function to advise the General Manager Nuclear Operations l

on all matters related to nuclear safety and shall provide review capability in the areas of:

a.

nuclear power plant operations b.

radiological safety c.

maintenance d.

nuclear engineering e.

nuclear power plant testing f.

technical advisory engineering g.

chemistry h.

quality control 1.

instrumentation and control COMPOSITION 6.5.1.2 The Onsite Safety Committee Supervisor is the OSC Chairman and shall l

appoint all members of the OSC.

The membership shall consist of a minimum of one individual from each of the ares designated in 6.5.1.1.

OSC members and alternates shall meet or exceee the minimum qualifications of ANSI N18.1-1971 Section 4.4 for comparable positions.

The nuclear power plant operations individual shall meet the qualifications of Section 4.2.2 and the maintenance individual shall meet the qualifications of Section 4.2.3.

i BEAVER VALLEY - UNIT 2 6-6 Anendment No. 38 l

ADMINI5TRATiVE CONTROLS COMPOSITION (Continued)

ALTERNATES

6. 5.1. 3 All alternate members shall be appointed in writing by the OSC Chairman to serve on a temporary basig; however, no more than two alternates shall participate as voting members in OSC activities at any one time.

MEETING FREQUENCY 6.5.1.4 The OSC shall meet at least once per calendar month and as convened by the OSC Chairman or his designated alternate.

QUORUM

6. 5.1. 5 A quorum of the OSC shall consist of the Chairman or his designated alternate and at least one half of the members including alternates.

RESPONSIBILITIE3 6.5.1.6 The OSC shall be responsible for:

a.

Review of 1) all procedures required by Specification 6.8 and changes of intent thereto, 2) any other proposed procedures or changes thereto as determined by tne General Manager Nuclear Operations to l

affeet nuclear safety, b.

Review of ali 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 including the preparation and forwarding of reports covering evalua-tion and recommendations to prevent recurrence to the General Manager, Nuclear Operations and to the Chairman of the Offsite Review Committee, f.

Review of all REPORTABLE EVENTS.

g.

Review of facility aperations to detect potential safety hazards, h.

Parforcance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Offsite Review Committee.

BEAVER VALLEY - UNIT 2 6-7 Amendment No. 7.38

ADMINISTRATIVE CONTROLS AUTHORITY

6. 5.1. 7 The OSC Shall:

a.

Recommend to the General Manager Nuclear Operations written approval l

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, c.

Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President i

Nuclear Group and the Offsite Review Committee of disagreement between the OSC and the; General Manager for Nuclear Operations however, General Manager for Nuclear Operations shall have respon-sibility for resolution of such disagreements pursuant to 6.1.1.

above.

RECORDS

6. 5.1. 8 The OSC shall maintain written minutes of each meeting and copies shall be provided to the General Manager Nuclear Operations and Chairman of the Offsite Review Committee.

6.5.2 0FFSITE REVIEW COMMITTEE (ORC) i i

FUNCTION i

6.5.2.1 The ORC shall function to provide independent review and audit of designated activities in the areas of:

1 a.

nuclear power plant operations b.

nuclear engineering c.

chemistry and radiochemistry d.

metallurgy e,

instrumentation and control t.

radiological safety g.

mechanical and electrical engineering h.

quality assuranco practices BEAVER VALLEY - UNIT 2 6-8 Amendment No. 7,38

ADMINISTRATIVE coWTROLS AUDITS (Continued) f.

The Facility Security Plan and implementing procedures at least once per 12 enths.

Any other area of facility operation considered appropriate by the g.

ORC or the Vice President, Nuclear, h.

The Facility Fire Protection Program and implementing procedures at least once per 24 months, i.

An independent fire protection and loss prevention program inspection and auciit shall be performed at least once per 12 months utilizing either qualified off-site licensee personnel or an outside fire protection firm, j.

An inspection and audit of the fire protection and loss prevention i

program shall be performed by a qualified outside fire consultant at least once per 36 months.

AUTHORITY

6. 5. 2. 9 The ORC shall report to and advise the Vice President Nuclear Group l

l on those areas of responsibility specified in Section 6.5.2.7 and 6.5.2.8.

RECORDS 6.5.2.10 Records of ORC activities shall be prepared, approved, and distri-buted as indicated by the following:

Minutes of each ORC meeting shall be prepared for and approved by a.

the ORC Chairman or Vice Chairman within 14 days following each meeting.

b.

Reports of reviews encompassed by Section 6.5.2.7 above, shall bo documented in the ORC meating minutes.

c.

Audit reports encompassed by Section 6.5.2.8 above, shall b'e forwarded to the Vice President, Nuclear Group and to the management positions l

responsible for the areas audited within 30 days after completion of the audit.-

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6.6 REPORTABLE EVENT ACTION l

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.

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. BEAVER VALLEY - UNIT 2 6-11 Amendment No. 7 i

i.

A

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

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

b.

The Safety Limit violation shall be reported to the Commission within one hour.

The Safety Limit violation shall be reported to the General Manager Nuclear 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, and (3) correc-tive action taken to prevent recurrence.

d.

The Safety Limit Violation Resort shall be submitted to the Commission, the-ORC and the General Manager, iuclear 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:

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

Guide 1.33, Revision 2, February 1978, b.

Refueling operations, Surveillance and test act!vit'es of safety related equipment.

c.

d.

Security Plan implementation.

e, Emergency Plan implementation, f.

Fire Protection Program implementation, g.

PROCESS CONTROL PROGRAM implementation.

h.

OFFSITE DOSE CALCULATION MANUAL implementation.

6.8.2 Each procedure ~'and administrative policy of 6.8.1 ' w e and changes of intent thereto, shall be reviewed by the OSC and approve o the_ General Mana-ger Nuclear Operations, predesignated alternate or a predesignated Manager to-whom the General Manager Nuclear Operations has assigned in writing the respon-e sibility for review and approval of specific subjects considered by the com-mittee, as applicable.

Changes to procedures and administrative policies or 6.8.1 above that do not receive OSC review, such as correcting typographical errors, reformatting _ procedures and other changes not affecting the purpose for

~ hich-the procedure.is performed shall receive an independent review by a w

-qualified individual and approved by a designated manager or director.

-BEAVER VALLEY - UNIT 2 6-12 Amendment No. 7.38 t

ADMINISTRATIVE CONTROLS PROCEDURE (Continued) 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

a.

The intent of the original procedure is not altered.

b.

The change is approved by two (2) members of the plant management staff, at least one (1) of whom holds a Senior Reactor Operator's License on the unit affected, The change is documented, reviewed by the OSC and approved by the c.

General Manager Nuclear Operations, predesignated alternate or a pre-designated Manager to whom the General Manager Nuclear Operations has assigned in writing the responsibility for review and approval of l

specific subjects, within 14 days of implementation.

6.8.4 APost-Accidentmonitorinfprovidethecapabilitytoobtainandanalyze program shall be established, implemented, and maintained.

The program wil reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples following an accident.

The pro-gram shall include the following:

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

6.8.5 A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation shall be implemented.

This program shall be described in the Ftation chemistry manual and shall include:

a.

Identification of a sampling schedule for the critical parameters and control points for these parameters; b.

Identification of the procedures used to measure the values of the critical parameters; c.

Identification for process sampling points; d.

Procedures for the recording and management of data; e.

Procedures defining corrective actions for off control point chemistry conditions; and f.

A procedure identifying:

1) the authority responsible for the interpretation of the data, and 2) the sequence and timing of administrative events required to initiate corrective action.

6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the U.S. Nuclear Regulatory Commission, Document Control Desk.

BEAVER VALLEY - UNIT 2 6-13 Amendment No. 7,14,38 c

1 ADM1hi1MI1YLCQNTROLS STARTUP REPOR15

6. 9.1.1 A summary report of plant startt.. and power escalation testing will be submitted following (1) receipt of an ope'ating license, (2) amendment to the license involving a planned increase in p u r level, (3) installation of fuel that has a different design or had been it '1tactured by a different fuel supplier, and (4) modifications that may have 5,ignificantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report sha address each of the tests identified in the FSAR and shall include a descr on of the measured values of the operating conditions or characteristics o ned during the test program and a comparison af these values with design pr6 o ions and specifications.

Any corrective actions that were required to obt.in satisfactory operation shall also be described.

Any additional specific details requested in license conditions based on other commitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following com-pletion of the startup test program, (2) 90 da mencement of commercial power operations, or (ys following resumption or com-

3) 9 months following initial criticality, whichever is earliest.

If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

ANNUAL REPORTS 2 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of each year.

The initial report shall be submitted prior to March 1 of the year following initial criticality.

6.9.1.5 Reports required on an annual basis shall include:

A tabulation of the number of station, utility, and othe personnel (includ-a.

ing contractors) receiving exposure greater t'ian 100 mrem /yr and their associated man-rem exposure according to work and job functions 2 (e, g,,

reactor operations and surveillance, inservice inspection, routine mainten-ance, special maintenance (describe maintenance), waste processing, and refueling).

The dose assignments to various duty functions may be esti-mated based on pocket dosimeter, TLD, or film badge measurements.

Small exposures totalling less than 20 percent of the individual total dose need not be accounted for.

In the aggregate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.

lA single submittal may be made for a multiple unit site.

The submittal should combine those sections that are common to all units at the site.

2This tabulation supplements the requirements of Section 20.407 of 10 CFR Part 20.

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BEAVER VALLEY - UNIT 2 6-14

, i ADMINISTRATIVE CONTROLS 6.14 PROCESS CONTROL PROGRAM (PCP)

FUNCTION 6.14.1 The PCP shall be those manuals, procedures, or references to procedures containing the processing steps, a set cf established process parameters and the steps detailing the program of sampling, analysis, and evaluation within which solidification of radioactive wastes is assured, consistent with Specifica-tion 3.11.3.1 and the surveillance requirements of these Technical Specifications.

6.14.2 Licensee initiated changes 1.

Shall become effective upon review and acceptance by the OSC.

6.15 0FFSITE DOSE CALCULATION MANUAL (ODCM)

FUNCTION 6.15.1 The ODCM shall describe the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints consistent with the applicable LCO's contained in these Technical Specifications.

Methodologies and calculational procedures acceptable to the Commission are contained in NUREG-0133.

6.15.2 Licensee initiated changes:

1.

Shall become effective upon review and acceptance by the OSC.

6.16 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS (Liquid, Gaseous and Solid)

FUNCTION 6.16.1 The radioactive waste treatment systems (liquid, gaseous and solid are those systems described in the facility Final Safety Analysis Report or Hazards Summary Report, and amendments thereto, which are used to maintain that control over radioactive materials in gaseous and liquid effluents and in solid waste packaged for offsite shipment required to meet the LCO's set forth in Specifica-tions 3.11.1.1, 3.11.1.2, 3.11.1.3, 3.11.1.4, 3.11.2.1, 3.11.2.2, 3.11.2.3, 3.11.2.4, 3.11.2.5, 3.11.2.6, 3.11.3.1 and 3.11.4.1.

6.16.2 MAJOR CHANGES as defined in Section 1 to the radioactive waste systems (liquid, gaseous and solid) shall be made by the following method:

A.

Licensee initiated changes:

1.

If a permanent facility change is made to a radioactive treatment system that could result in an increase in the volume or activity discharged, the Commission shall be informed by the inclusion of a BEAVER VALLEY - UNIT 2 6-23 Amendment No. 14

ADMINISTRATIVE CONTROLS FUNC110N (Continued) 2.

10 CFR Part 50, Section 50.34a(b)(2) requires that each application to construct a nuclear power reactor provide an estimate of the quan-tity of radionuclides expected to be released annually to unrestricted areas in liquid and gaseous effluents produced during normal reactor operation.

3.

10 CFR Part 50, Section 50.34a(3) requires that each application to construct a nuclear power reactor provide a description of the provisions for packaging, storage and shipment offsite of solid waste containing radioactive materials resulting from treatment of gaseous and liquid effluents and from other sources.

4.

10 CFR Part 50, Section 50.34a(3)(c) requires that each application to operate a nuclear power reactor shall include (1) a description of the equipment and procedures for the control of gaseous and liquid effluents and for the maintenance and use of equipment installed in radioactive waste systems and (2) a revised estimate of the information required in (b)(2) if the expected releases and exposures differ significantly from the estimate submitted in the application for a construction permit.

5.

The Regulatory staff's Safety Evaluation Report and amendments thereto issued prior to the isst.ance of an operating license contains a description of the radioactive waste systems installed in the nuclear power reactor and a detailed evaluation (including estimated releases of radioactive materials in liquid and gaseous waste and qtantities of solid waste produced from nora l operation, estimated annual maxi-mum exposures to an individual in the u.1 restricted area and estimated exposures to the general population) which shows the capability of these systems to meet the appropriate regulations.

6.17 RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM The General Manager Nuclear Operations delegates the responsibility for the Radiological Environmental Monitoring Program to the Health Physics Manager or his designated alternate.

The Health Physics Manager is responsible for administering the offsite l

Radiolo0ical Environmental Monitoring Program.

He shall determine that the sampling program is being implemented as described to verify that the environ-ment is adequately protected under existing procedures.

He shall also have the responsibility for establishing, implementing, maintaining and approving offsite environmental program sampling, analyses and calibration procedures.

BEAVER VALLEY - UNIT 2 6-24 Amendment No. 7,38 1

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