ML20207M302
| ML20207M302 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/06/1988 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duquesne Light Co, Ohio Edison Co, Pennsylvania Power Co |
| Shared Package | |
| ML20207M305 | List: |
| References | |
| DPR-66-A-131, GL-88-006, NPF-73-A-007 NUDOCS 8810180221 | |
| Download: ML20207M302 (26) | |
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UNITED STATES
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DUQUESNELIpHT_COMPAN,Y OHIO EDISON COMPANY PENNSYLV_ANIA POWER COMPANY DOCKET NO. 50-334 BEAVER VALLE,Y,P0KER g gj g,yjl g,1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 131 License No. DPR-66 1.
The Nuc' ar Regulatory Conmission (the Comission) has found that:
A.
The application for amendment by Duquesne Light Company, et al.
(the licensee) dated June 11, 1988 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFP Chapter It B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Conmission; C.
There is reasonable assurance (i) that the activities authorized by this atendrent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The inuance of this anendment will not be inimical to the comon dvense and security or to the health and safety of the public; and E.
The issuance of this anendnent is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirerents have been satisfied.
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0010180221 881006 PDR ADOCK 05000334 P
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C 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachnent to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-66 is hereby amended to read as follows:
(2),Technj,ca1, Speci fications e
The Technical Specifications contained in Appendix A, as revised through Amendment No.131 are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license anendment is effective on issuance, to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION O
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. Stolz,'Directo Project Directorate
-4 Jivisinn of Reactor Projects I/II Office of Nuclear Reactor Regulatien
Attachment:
Changes to the Technical Specifications Cate of Issuance: October 6,1988
- ,; 1s e.
s ATTACPMENT_TOLLCENSEJMENpMENTNp.131 E
FACILITY OPERATING LICENSE NO. DPR-66 00CKET h0. 50-334~
i 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.
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Perove Insert 6-1 6-1 I
6-la 6-2 6-2 6-3
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6-3 6-6 6-6 6-7 6-7 l
t 6-8 6-8 6-11 6-11 6-12 6-12 6-13 6-13 6-31 6-31 l
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ADMINISTRATIVE CONTROLS
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6.1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overal* "
operation and shall delegate in writing the succession tc 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, re:pectively.
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, an appropriate, in the form of o*ganization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions fer key personnel positions, or in equivalent forms of documentation.
These requirements shall be documented in the FSAR.
b.
The Plant Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
1 c.
The Vice President Nuclear Group shall have corporate responsibility for overall plant nuclear safety and shall take l
any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nucicar safety.
d.
The individuals who train the operating staff and those who carry out hcalth 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 D44,131
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ADMINISTRATIVE CONTROLS 6.2.2 UNIT STAFF The unit 'rganization shall be subject to the following:
l a.
Each on 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.
d.
An individual qualified in radiation protection procedures shall be onsite when fuel is in the reactor.
c.
ALL CORE ALTERATIONS after the initial fuel loading shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Opers. tor Limited to Fuel Handling who has no other concurrent responsibilities during this operat!.on.
f.
A Fire Brigade of at least 5 members shall be maintained on site at all times.
The Fire Brigade shall not include 3 members of the minimum shift crew necessary for safe shutdown of the unit or any personne'l required for other essential functions during a fire emergency.
g.
Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions; renior reactor operators, reactor operators, radiation control technicians, auxiliary operators, meter and control repairm n, and all personnel actually performing work on 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 unforseen problems require subatantial 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 vork 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 timo.
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.
BEAVER VALLEY - UNIT 1 6-2 Amenchent flo. 74.144,131
ADMINISTRATIVE CONTROLS 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 Plant Manager or predesignated alternate, or 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 flo. W. h0.131 l
1 I
ADMINISTRATIVE CONTROLS m.
ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the 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
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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.
I QUORUM 6.b.l.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.
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RESPONSIBILITIES t
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 cther proposed procedures or changes thereto as determined by the Plant Manager 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.
I 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 i
of reports covering evaluation and recommendations to prevent recurrence to the General
- Manager, Nuclear l
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, M. W.131
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ADMINISTRATIVE CONTROLS AUTHORITY 6.5.1.7 The OSC shall:
a.
Recommend to the Plant Manager written 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 General l
Manager Nuclear Operations and the Offsite Review Committee of disagreement between the OSC and the Plant Manager;
- however, the Plant Manager 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 l
and Chairman of the Offsite Review Committee.
6.5.2 OFFSITE REVIEW COMMITTEE (ORC)
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 b.
nuclear engineering c.
chemistry and radiochemistry i
i d.
metallurgy e.
instrumentation and control I
f.
radiological safety I
g.
mechanical and electrical engineering h.
quality assurance practices BEAVER VALLEY - UNIT 1 6-7 Amendment flo. '6Z, M 131 I
4 1
6 ADMINISTRATIVE CONTROLS
, COMPOSITION 6.5.2.2 The chairman and all members of the ORC shall be appointed by the Vice President, Nuclear Group.
The membership shall consist l
of a
minimum of five individuals who collectively possess a broad based level of experience and competence enabling the committee to review and audit those activities designated in 6.5.2.1 above and to recognize when it is necessary to obtain technical advice and counsel.
An individual may possess expertise in more than one speciality area.
The collective competence of the committee will be maintained as changes to the membership are made.
ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the ORC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in ORC activities at any one time.
CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the ORC Chairman to provide expert advice to the ORC.
BEAVER VALLEY - UNIT 1 6-8 Amendment No. bi it0.131
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ADMINISTRATIVE CONTROLS n
i
'i s AUTHORITY l
0 6.5.2.9 The ORC shall report to and advise the Vice President, l
Nuclear Group 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 t
distributed as indicated by the following:
a.
Minutes of each ORC meeting shall be prepared for and approved by 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 be documented in the ORC meeting minutes.
c.
Audit reports encompassed by Section 6.5.2.8 above, shall be l
forwarded to the Vice President, Nuclear Group and to the l
management positions responsible for the areas audited within 30 days after completion of the audit.
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 i
and/or a
report be submitted pursuant to the requirements of Section 50.73 to 10CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the OSC, and results of this review shall be submitted to the ORC.
f 6.7 SAFETY LIMIT VIOLATION f
6.7.1 The following actions shall be taken in the event a safety l
Limit is violated:
a.
The facility shall be placed in at least HOT STANDBY within one (1) hour.
b.
The Safety Limit violation shall be reported to the Commission within one hour and to the General Nanager. Nuclear Operations and to the ORC l
within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
BEAVER VALLEY - UNIT 1 6-11 Amendment No. M. he. M.131
' ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION (Continued) 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 d..
The Safety Limit Violation Report shall be submitted to tha l
Commission, the ORC and the General Manager, Nuclear Operations
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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 reisted equipment.
d.
Security Plan implementation.
e.
Emergency Plan impler.entation.
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 6.6.1 above and changes of intent thereto, shall be reviewed by the OSC and approved by the Plant
- Manager, predesignated alternate or a predesignated Manager to whom the Plant Manager has assigned in writing the responsibility for review and approval of specific subjects considered by the committee, as applicable.
Changes to proceduras and administrative policies of 6.8.1 above that do not receive OSC
- review, such as correcting typographical
- errors, reformatting procedures and other changes not affecting th2 purpose for which the procedure is performed shall receive an independent review by a qualified individual and approved by a
designated manager or director.
BEAVER VALLEY - UNIT 1 6-12 Amendment No '%, t% MQ,131
ADMINISTRATIVE CORTROLS 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 Plant
- Manager, predesignated alternate or a
predesignated Manager to whom the Plant Manger 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 tne following:
(i)
Training of personnel, (ii)
Procedures for sampling and analysis, and (iii)
Provisions for maintenance of sampling and analysis equ'ipment.
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; identification for process sampling polpts; l
c.
d.
Procedures for the recording and management of data; e.
Procedures defining corrective actions for off control point chemistry conditions; and f.
A procedure identifyin'g:
1) the authority responsible for the interpretation of the data, and i
4 2) the sequence and timing of administrative events required to initiate corrective action.
4 BEAVER VALLEY - UNIT 1 6-13 Amendment No.H. M5 M4.
142. 131
A.
I ADMINISTRATIVE CONTROLS 6.17 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The General Manager Nuclear Operations delegates the responsibility l
for the Padiological Environmental Monitoring Program to the Radiological Control Manager or his designated alternate.
l The Radiological Control Manager is responsible for administering the offsite Radiological Environmental Monitoring Program.
He shall determine that the sampling program is being implemented as described l
to verify that the environment is adequately protected under existing procedures.
He shall also have the responsibility for establishing, i
implementing, maintaining and approving offsito environmental program sampling, analyses and calibration procedures.
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BEAVER VALLEY - UNIT 1 6-31 Amendment No. M. hC.131
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UNITED STATES
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g NUCLEAR REGULATORY COMMISSION 3
E WASHING TON, D. C. 20665
'4,***** $
DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY THE CLEVELAND ELECTRIC ILLl'MINATING COMPANY THE TOLEDO rDISON COMPANY DOCKET NO. 50-412 E58253.28lb E.Pg,E3,gp,TIO L UNIT NO 2 APENDMENT TO FACILITY OPERATING LICENSE Amendment No. 7 License No. NPF-73 1.
The Nuclear Regulatory Conmission (the Cor. mission) has found that:
A.
The application for anendment by Duquesne Light Company, et al.
(the licensee) dated June 11, 1988 complies with the standards and requirements of the Atomic Energy Act of 1954, a3 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 Conrnission; C.
There is reasonable assurance (1) 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 Commission's regulations; D.
The issuance of this amendeent will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendaent is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirenents have been satisfied.
f i
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.A 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachn;ent to this license amendrrent, and paragraph ?.C.(2) of Facility Operating License No. DPR-66 is hereby amended to reed as follows:
(2) Technical Spe,c,if,1, cations The Technical Specifications contained in Appendix A, as revised through Amendnent No. 7, and the Environnental Protection Plan contr.ined 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 Envirornental Protection Plan.
3.
This license aniendnent is effective on issuance, to be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COPMISSION O.
ob F. Stolz, Direct Pro' ject DirectorateT-4 Df' vision of Reactor Projects I/II C'ffice of Nuclear Peactor Regulation Attachrent:
Charges to the Technical Specificatiens Cate of Issuarce: October 6, 1988
,f
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ATTACHMENT TO LICFNSE AMENDMENT NO. 7 FACILITY OPERATING LICENSE NO. NPF-73 DOCKET NO. 50-412 Replace the following pages of the Appendix A Technical Specifications l
with the enclosed pages as indicated. The revised pages are identified by amendnent number and contain vertical lines indicating the areas of change.
P Remove Insert 6-1 6-1 6-2 6-2 6-3 6-3 6-4 6-7 6-7 6-8 6-8 6-9 6-9 6-11 6-11 6-12 6-12 6-13 6-13 6-24 6-24
J 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.
l 6.2 ORGANIZATION t
6.2.1 ONSITE AND OFFSITE ORGANIZATIONS i
Onsite and offsite organizations shall be established for facility oporation and corporate management, respectively.
The onsite and offsite organizations shall include the positions for activities affectina the safety of the nuclear l
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 l
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 Plant Manager shall be responsible for overall unit safe operation l
and shall have control over those onsite activities necessary for safe l
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 f
acceptable performance of the staff in operating, maintaining, and L
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, l
6.2.2 UNIT STAFF The unit organization shall be subject to the following:
f a.
Each duty shift shall be composed of at least the minimum shift crew I
composition shown in Table 6.2-1.
l b.
At least one licensed Operator shall be in the control room when fuel is in the reactor.
j c.
At least two licensed Operators shall be in the control room during resctor start-up, scheduled reactor shutdown and during recovery from reactor trips.
BEAVER VALLEY - UNIT 2 6-1 Amendment No. 7
ADMINISTRATIVE CONTROLS UNIT STAFF (Continued) 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 Roactor 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 implement 2d to limit the working hours of unit staff who perform saf aty-related functions; senior reactor operators, reactor operators, radiation control 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 normal 8-hour day, 40-hour week while the plant is opertting.
However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutoown 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 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 shif t turnover time.
c.
A break of at least eight hours should be allowed betwean work periods, including shift turnover time.
d.
Except during extended shutdown periods, the use of overtime should be considsred on an individual basis and not for the entire staff on a shift.
Any deviation from the above guidelines shall be authorized by the Plant Manager or predesignated alternate, or higher levels of manage-
~
ment.
Authorized deviations to the working hour guidelines shall be docuented and available for NRC review.
6.2.3 INDEPENDENT SAFETY EVALUATION GROUP (ISEG)
FUNCTION 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 de'. led recommendations for revised procedures, equipment modifications, maintenai::e activities, operations activities, or other means of improving unit safety to corporate management.
If not otherwise implemented, all recommenda-tions shall then be made to the Vice President, Nuclear Group.
BEAVER VALLEY - UNIT 2 6-2 Amendment No. 7 1
ADMINISTRATIVE CONTROLS COMPOSITION 6.2.3.2 The ISEG shall be composed of at least five, dedicated, full-time engineers located on site.
Each shall have a bachelor's degree in engineering or related science and at least 2 years professional level experience in his field, at least 1 year of which experience shall be in the nuclear field.
RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of unit activities to prcvide independent verification
- that these activities arc performed correctly and that human errors are reduced as much as practical.
RECORDS 6.2.3.4 Records of activities performed by the ISEG shall be prepared, main-tained, and a summary report shall be forwarded each calendar month to the Vice l
President, Nuclear Group.
INot responsible for sign-off function.
BEAVER VALLEY - UNIT 2 6-3 (next page is 6-5)
Amendmant No. 7 l
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ADMINISTRATIVE CONTROLS COMPOSITION (Continued)
ALTERNATES t
6.5.1.3 All alternate members shall be appointed in writing by the 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.
1 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.
7 QUORUM i
1 6.5.1.5 A quorum of the OSC shall consist of the Chairman or his designated i
alternate and at least one half of the members including alternates, i
J RESPONSIBILITIES 6.5.1.6 The OSC shall be responsible for:
f 1
a.
Review of 1) all procedures required by Specification 6.8 and changes
[
i of intent thereto, 2) any other proposed procedures or changes
[
thereto as determined by the Plant Manager to affect nuclear safety.
b.
Review of all proposed tests and experiments that affect nuclear i
safety.
c.
Review of all proposed changes to the Technical Specifications.
(
i d.
Review of all proposed changes or modifications to plant systems or i
equipment that affect nuclear safety.
4 I
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 l
l
{
Manager, Nuclear Operations and to the Chairman of the Offsite Review Committee.
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f i
f.
Review of all REPORTABLE EVENTS.
j g.
Review of facility operations to detect potential cafety hazards, f
l h.
Performance of special reviews, investigations or analyses and reports j
thereon as requested by the Chairman of the Offsite Review Committee, i
a t
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BEWER VALLEY - UNIT 2 6-7 Amendment No. 7 l
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" t ADMINISTRATIVE CONTROLS i
AUTHORITY 6.5.1.7 The OSC Shall:
I a.
. Recommend to the Plant Manager written 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 I
iteu 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 General Manager l
Nuclear Operations and the Offsite Review Committee of disagreement between the OSC and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements 1
pursuant to 6.1.1. above.
i RECORDS I
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 l i
Review Committee.
6.5.2 0FFSITE REVIEW COMMITTEE (ORC) l J
f iUNCTION 6.5.2.1 The ORC shall function to provide independent review and audit of l
designated activities in the areas of:
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a.
nuclear power plant operations l
b.
nuclear engineering 2
I c.
chemistry and radiochemistry d.
metallurgy l
e.
instrumentation and control l
f.
radiological safety
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mechanical and electrical engineering j
h.
quality assurance practices 1
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l BEAVER VALLEY - UNIT 2 6-8 Amendment No. 7 1
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ADMINISTRATIVE CONTRGLS COMPOSITION 6.5.2.2 The chairman and all members of the ORC shall be appointed by the l
Vice President, Nuclear Group.
The membership shall consist of a minimum of l
l five individuals who collectively possess a broad based level of experience and competence enabling the committee to review and audit those activities designated
[
in 6.5.2.1 above and to recognize when it is necessary to obtain technical advice and counsel.
An individual may possess expertise in more than one speciality area.
The collective competence of the committee will be maintained as changes to the membership are made.
i ALTERNATES j
6.5.2.3 All alternate members shall be appointed in writing by the ORC i
Chairman to serve on a temporary basis; however, no more than two alternates shtll participate as voting members in ORC activities at any one time.
CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the ORC Chairman to provide expert advice to the ORC.
l MEETING FREQUENCY
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6.5.2.5 The ORC shall meet at least once per calendar nuarter during the
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initial year of facility operation following fuel load q and at least once per six months thereaf ter.
0VORUM f
6.5.2.6 A quorum of ORC shall consist of the Chairman or his designated alter-f nate and at least four members including alternates.
No more than a minority of the quorum shall have line responsibility for operation of the facility.
REVIEW I
6.5.2.7 The ORC shall review:
}
a.
The safety evaluations for 1) changes to procedures, equipment, or i
systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not consitute an unreviewed safety question.
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BEAVER VALLEY - UNIT 2 6-9 Amendn.ent No. 7 I
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m._,,,,,
ADMINISTRATIVE CONTROLS AVOTTS (Continued) f.
The Facility Security Plan and implementing procedures at least once per 12 months.
g.
Any other area o' facility operation considereu appropriate by the 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 audit 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 program shall be perfornied by a qualifieu 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
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 be documented in the ORC meeting minutes, c.
Audit reports encompassed by Section 6.5.2.8 above, shall be 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.
- 6. 6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
a.
The Commission shall be notifieu 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.
BEAVER VALLEY - UNIT 2 6-11 Amendment No. 7
o ADMINISTRATIVE CONTROLS 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 within one (1) hour, 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 l
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 Conimittee (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 Safett t Violation Report shall be submitted to the Commission, the ORC and s v tral Manager, Nuclear Operations within 30 days of the l
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, c.
Surveillance and test activities of safety related equipment, d.
Security Plan implementation, e.
Emergency Plan implementation, f.
Fire Protection Program implementation, g.
PROCESS CONTROL PROGRAM implementation.
h.
OFFSITE DOSE CALCJLATION MANUAL implementation.
6.8.2 Each procedu'e and administrative policy of 6.8.1 above and changes of intent thereto, shrll be reviewed by the OSC and approved by the Plant Manager, predesignated alte nate or a predesignated Manager to whom the Plant Manager 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 receive 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.
BEAVER VALLEY - UNIT 2 6-12 Amendment No. 7
i 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.
c.
The change is documented, reviewed by the OSC and approved by the Plant Manager, predesignated alternate or a predesignated Manager to whom the Plant Manager has assigned in writing the responsibility I
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.
The program will provide the capability to obtain and analyze i
reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples following an accident.
The pro-gram shall include the following:
3 (i) Training of personnel, i
(ii) Procedures for sampling and analysis, and l
(iii) Provisions for maintenance of sampling and analysic equipment.
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f 3. 5 A program for monitoring of secondary water chemistry to inhibit steam i
generator tube degradation shall be implemented.
This program shall be l
il described in the station chemistry manual and t. hall include:
j a.
Identification of a sampling schedule for the critical parameters and l
centrol point > for these parameters; b.
Identification of the procedures used to measure the values of the critical parameters; c.
Identification for process sampling points; j
d.
Procedures for the recording and management of data; e.
Procedures oefining corrective actions for off control point chemistry conditions; and j
f.
A procedure identifying; l
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1) the authority responi,ible for the interpretation of the data, and f
2) the sequence and timing of administrative events required to initiate corrective action, j
6.9 REPORTING REQUIREMENTS l
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ROUTINE REPORTS l
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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 Regional Administrator of the Regional Office of the NRC unless otherwise noted.
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l BEAVER VALLEY - UMIT 2 6-13 Amendment No. 7 I
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ADMINISTRATIVE CONTROLS FUNCTION (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 pows reactor provide a description of the provisions for packagir, storage and shipment offsite of solid waste containing radioactive._sterials 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 issuance 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 quantities of solid waste produced from normal operation, estimated annual maxi-mum exposures to an individual in the unrestricted area and estimated exposures to the general population) which shows the capability of these systems to meet the appropriate regulations.
6.17 RADIOLOGICAL ENVIRONMENTAL MONITORINO PROGRAM The General Manager Nuclear Operations delegates the responsibility for l
the Radiological Environmental Monitoring Program to the Radiological Con +rol Manager or.his designated alternate.
I The Radiological Control Manager is responsible for administering the offsite Radiological Environmental Monitoring Program.
He shall dete'.mine 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 4
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