ML20205H689

Corrected Amends 68 & 57 to Licenses NPF-10 & NPF-15, Respectively,Deleting Onsite & Offsite Organization Charts & Revising Reporting Responsibility of Independent Safety Engineering Group & Nuclear Safety Group

ML20205H689
Person / Time
Site:	San Onofre
Issue date:	10/18/1988
From:	Knighton G Office of Nuclear Reactor Regulation
To:
Shared Package
ML20205H692	List: ML20205H689
References
TAC-54700, TAC-54701, NUDOCS 8810310142
Download: ML20205H689 (26)

Text

.

/

UMTED 8TATES

[*

NUCLEAR REGULATORY COMMISSION 3

WASHINGTON, D C. 20004 k*....

SOUTHERN CALIFORNIA EDISON COMPANY 4

SAN DIEGO GAS AND ELECTRIC COMPANY i

THE CITY OF RIVERSIDE. CALIFORNIA

}

THE CITY OF ANAHEIM. CALIFORNIA i

DOCKET NO. 50-361 i

SAN ONOFRE NUCLEAR GENERATING STATION. UNIT NO. 2

}

AMEN 0 MENT TO FACILITY OPERATING LICENSE

+

r Amendment flo. 68 i

License No. NPF-10 l

1.

The Nuclear Regulatory Comission (the Comission) has found that:

f 4.

l A.

The application for amendment to the license ter San Onofre l

l Nuclear Generating Station, Unit 2 (the facility) filed by.

t Southern California Edison Company (SCE) on behalf of itself and San Diego Gas and Electric Company, the City of Riverside, i

California and the City of Anaheim, California (licensees) j j

dated September 13, 1988 complies with the standards and requirements t

of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; i

8.

The facility will operate in conformity with the application, f

the provisions of the Act, and the regulations of the Comission; 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 Comission's regulations; l

4 D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and 4

E.

The issuance of this amendment is in accordance with 10 CFR Part i

51 of the Comission's regulations and all applicable requirerents l

have been satisfiec.

j i

l i

?!?*igfCKC3000361 42 es1ose 1

P

+

t PDC

[

2 2.

Accordingly, the license is amended by changes to the Technical Spect-fications as indicated in the attachment to this license amendment, ar.o paragraph 2.C(2) of Facility Operating License No. NPF-10 is hereby anended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 68, are hereby incorporated in the license. SCE shall operate the facility in accordance with the Technical Specifications and the Environrental Protection Plan.

3.

This license amendrent is effective as of the date of its issuance and rust be fully implemented no later than 30 days from the date of issuance.

FOR THE NUCLEAR RE ULATORY COMMISSION 44ff IQ eorge Al. Knighton, Director Projedt Direct 6 rate Y Division of Reactor Projects - !!!,

IV, Y and Special Projects

Attachment:

Changes to the Technical Specifications Date of issuance: October 18, 1988

o 4

ATTACHMENT TO LICENSE AMENDMENT 110. 68 FACILITY OPERATING LICENSE h0. NPF-10 DOCKET NO. 50-361 Revise Appendix A Technical Cpecifications by removing the pages identified f

below and inserting the enclrsed pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.

Also enclosed are the following overleaf pages to the amended pages.

1 AMEh0HENT PAGE OVERLEAF PAGE 6-1 6-la 6-2 6-3 6-4 6-5 6-0 6-12 6-11 9

l

+

i

.____.__m__,__,_

ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Station Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 The Shift Supervisor (or during his absence from the Control Room Area, a designated individual) shall be responsible for the Control Room command function.

A management directive to this effect, signed by the Vice-President of Nuclear Operations shall be reissued to all station personnel on an annual basis.

6.2 ORGANIZATION OFFSITE 6.2.1 Onsite and offsite organizations shall be established for unit 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, respnsibility, 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 descrip-tions of departmental responsibilities and reir'ionships, and job descriptions for key personnel positions, or in equivalent forms of documentation.

These requirements shall be documented in the FSAR.

b.

The Station 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.

The Vice President, Nuclear Engineering, Safety, and Licensing and c.

the Vice President and Site Manager shall have corporate responsibil-ity for overall plant nuclear safety.

The Vice President and Site Manager shall take any measures needed to ensure acceptable perform-ante of the staff in operating and maintaining the plant to ensure nuclear safety.

The Vice President, Nuclear Engineering, Safety and Licensing shall tcke any measures needed to ensure acceptable performance of the staff in 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; hnwever, they shall have sufficient organizational freedom to ensu e their independence from operating pressures.

SAN ONOFRE-UNIT 2 6-1 AMENDMENT NO. 68

ADMINISTRATIVE CONTROLS UNIT STAFF 6.2.2

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 Reactor Operator shall be in the Control Room when fuel is in the reactor.

In addition, while the unit is in MODE 1, 2, 3 or 4, at least one licensed Senior Reactor Operator shall be in the Control Rocm area identified as such on Table 6.2-1.

c. A health physics technician # shall be on site when fuel is in the

reactor,

d. All CORE ALTERATIONS shall be observed and 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.

e. A site Fire Bpigade of at least 5 members shall be maintained onsite at all times.

The Fire Brigade shall not include the Shif t Super-visor and the 2 other members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.

f. Reserved.

g. The Plant Superintendent (at time of appointmeat), Shift Superintendents and Control Room Supervisors shall hold a senior reactor operator license.

The Control Operators and Assistant Centrol Operators shall hold a reactor operator license.

I The health physics technician and Fire Brigade composition may be 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 provided immediate action is taken to fill the required positions.

5 t

SAN ONOFRE-UNIT 2 6-la AMENDMENT NO. 68

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

-e

,~

,--.-._.-.--------n-e-

t 1

1 4

i (This page intentionally blank) l.i l.

L SAN ONOFRE-UNIT 2 6-2 AMENDMENT NO. 68

t (This page intentionally blank) i SAN ONOFRE-UNIT 2 6-3 AMENDMENT NO. 68

Table 6.2-1 MINIMUM SHIFT CREW COMPOSITION i

WITH UNIT 3 IN MODE 5 OR 6 OR DE-FUELED POSITION NUMBER OF INDIVIOUALS REQUIRED TO FILL POSITICN MODES 1, 2,'3 & 4 MODES 5 & 6 8

SS l'

1 SRO 1

None R0 2

1 D A0 2

2 l

STA 1

None WITH UNIT 3 IN PODE 1, 2, 3 or 4 POSITION NUMBER OF INDIVIOUALS REQUIRED TO FILL POSITION MODES 1, 2, 3 & 4 MODES b & 6 SS l "'

1" SRO 1

Nons D

RO 2

1 D

A0 2

1 a

STA l

None

' Individual may fill the same position on Unit 3 One of the two required individuals may fill the same position on Unit 3 Shift Supervisor with a Senior Reactor Operators License on Ur.its 2 SS and 3 Individual with a Senior Reactor Operators License on Units 2 and 3 SRO Individual with a Reactor Operators License on Units 2 and 3 RO Auxiliary Operator A0 Shift Technical Advisor STA Except for the Shift Supervisor, the Shift Crew Composition may be one less than the minimum requirements of Table 6.2-1 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 accor.modate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the Shift Crew Composi-l tion to within the minimum requirements of Table 6.2-1.

This provision does not permit any shift crew position to be unmanned upon shift change due to an l

oncoming shift crewman being late or absent, l

Ouring any absence of the Shif t Supervisor from the Control Room Area shown in Figure 6.2-3 while the unit is in MODE 1, 2, 3 or 4, an individual (other than i

the Shift Technical Advisor) with a valid SRO license shall be designated to assume the Control Room cor. mand function. During any absence of the Shif t Supervi4or from the Control Room Area shown in Figure 6.2-3 while the unit is in MODE 5 or 6, an individual with a valid SR0 or R0 license shall be designated i

to assume the Control Room command function.

SAN ONOFRE UNIT 2 6-4 Amendment No.16 1

2 l

ADMINISTRATIVE CONTROLS 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)

FUNCTION 6.2.3.1 The ISEG shall function to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports and other sources of plant design and operating experience information which may indicate areas for improving plant safety.

COMPOSITION 6.2.3.2 The ISEG shall be composed of at least five dedicated full-time engineers.

Each shall have a Bachelor's Degree in Engineering or Physical Science or equivalent and at least two years professional level experience in his field.

Off-duty qualified Shift Technical Advisors may be used to fulfill this requirement.

RESPONSIBILITIES 6.2.3.3 The ISEG shall be.'esponsible for maintaining surveillance of plant activities to provide independtnt verification

• that these activities are performed correctly and that huean errors are reduced as much as practical.

AUTHORITY l

6.2.3.4 The ISEG shall make detailed recommendation. for revised procedures, equipment modifications, maintenance activities, operations activities or other means of improving plant safety to offrite organization management.

l RECORDS l

6.2.3.5 Records of activities performed by the ISEG shall be prepared, maintained, and forwarded each calendar month to offsite organizaticn i

management.

I 6.2.4 SHIFT TECHNICAL ADVISOR The Shift Technical Advisor shall provide technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering and plant analysis with regard to the safe operation of the unit.

The Shift Technical Advisor shall have a Bachelor's Degree or equivalent in a scientific or engineering discipline with specific training in plant design and in the response and analysis of the plant for transients and accidents, l

6.3 UNIT STAFF QUALIFICATIONS t

6.3.1 Each member of the unit 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 of Regulatory Guide 1.8, September 1975.

" ot responsible for sign-off function.

N SAN ONOFRE-UNIT 2 6-5 AMENDHENT NO.

8

ACHINISTRATIVE CONTROLS 6.4 TRAIN!NG

~

6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the cirection of the Manager, Nuclear Training and shall meet or exceed the recuirements and recommendations of Sections 5.5 of ANSI N18.1-1971 and A:pendix A" of 10 CFR part 55 and the supplemental recuirements specified in Section A and C of Enclosure 1 of the March 28, 1920 NRC letter to all licensees, and shall incluce familiari:ation with relevant incustry operational experience icentified by the 15EG.

6.5 REVIEW AND AUDIT

6. 5.1 ONSITE REVIEW COMMITTEE (OSRC)

FUNCTICN

6. 5.1.1 The Onsite Review Com.91ttee shall function to advise the Station Manager en all matters related to nuclear safety.

C0Y05! TION

6. 5.1. 2 The Onsite Review Co?.mittee shall be composed of the:

Chairman:

Station Manager Mercer:

Deputy Station Manager Member:

Manager, Operations I

Meeter:

Manager Technical Member:

Plant Superintencent SCNGS Unit 2 & 3 Me?:er:

Supervisor of !&C Member:

Manager, Health Physics l

Member:

Supervisor of Chemistry a

Meteer:

Manager, Maintenance l

Member:

Sucervising Engineer (N555, N555 Support, Computer, or STA)

Membe r:

SanDiegoGas&q{}ectricRepresentative, Senior Engineer ALTERNATES

6. 5.1. 3 All alternate mesters shall be appointed in writing by the 05RC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting memeers in 05RC activities at any one time, (1385 degree in Engineering or Physical Science plus at least four years professional level experience in his field.

At least one of the four years experience shall be nuclear power plant experience.

SAN CNCFRE-UNIT 2 6-6 Amendment No. 4

ADMINISTRA7!VE CONTROLS d.

Proposed changes to Technical Specifications or this Ocerating License.

Violations of codes, regulations, orders, Technical Specifications, e.

license requirements, or of internal procedures or instructions having nuclear safety significance, f.

Significant c:erating abnormalities or deviations from noresi and expected performance of unit equipment that affect nuclear safety, Events recuiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commission, g.

h.

All recognized indications of an unanticipated deficiency in some aspect of design or operati3n of structures, systems, or components that ceule affect nuclear safety.

i.

Reports and meetings minutes of the Onsite Review C mmittee.

AUDITS 6.5.3.5 Audits of unit activities shall be performed uncer the c:gni:ance of the NSG.

These aucits shall encompass:

The conformance of unit oceration to provisions containee within the a.

Technical Specifications and applicable license conoitions at least once per 12 months.

b.

The performance, training and qualifications of the entire unit staff at least once per 12 months, The results of actions taken to correct deficiencies occurring in c.

unit equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.

d.

The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appencix "B",10 CFR 50, at least once per 24 months, Any other area of unit operation considered appropriate by the e.

Nuclear Safety Group or Manager of Nuclear Operations.

f.

The Fire Protection Program and implementing procedures at least I

once per 24 months.

An independent fire protection and loss prevention inspection and g.

audit shall be performed annually utilizing either qualified 'offsite licensee personnel or an outside fire protection firm.

An inspection and audit of the fire protection and loss preventien h.

program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.

AMENDMENT No.16 SAN ONCFRE-UNIT 2 6-11

ADMINISTRATIVE CONTROLS AUTHORITY 6.5.3.6 The NSG shall report to and advise the offsite organization management on those areas of responsibility specified in Sections 6.5.3.4 and 6.5.3.5.

[

RECORDS 6.5.3.7 Records of NSG activities shall be prepared and maintained.

Report of reviews and audits shall be distributed monthly to the Station Manager and to the management positions responsible for the areas audited.

i f

l i

E I

i i

f

[

SAN ONOFRE-UNIT 2 6-12 AMENDMENT NO. 68

r

/,

UNITED STATES y

n NUCLEAR REGULATORY COMMISSION 3

W A8841NG70*d, D. C. 20004 o......

SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVER $10E. CALIFORNIA THE CITY OF ANAHE!M. CALIFORNIA I

DOCKET NO. 50-362 SAN ONOFRE NUCLEAR GENERATING STATION. UNIT NO. 3 l

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 57 License No. NPF-15 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment to the lie:ense for San Onofre Nuclear Generating Station Unit 2 (the facility) filed by Southern California Edison Corrpany (SCE) on behalf of itself and San Diego Gas and Electric Corpany the City of Riverside, i

CaliforniaandtheCityofAnaheim, California (licensees) dated September 13, 1988 complits with the standards and requirements r

of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I; B.

The facility will o>erate in ccMormity with the application,

(

the provisions of tie Act, and the regulations of tie Comission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health i

and safety of the public, and (ii) that such activities will be

{

conducted in compliance with the Comission's regulations, D.

The issuance of this amendment will not be inimical to the comen defense and security or to the health and safety of the public; and f

t E.

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

I i

[

l t

I

2.

Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, ard paragraph 2.C(2) of Facility Operating License No NPF-15 is hereby amended to read as follows:

1 (2) Technical Specifications The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appandix B, t

as revised through Amendment No. 57, are hereby incorporated in the license. SCE shall operate the facility in accordance with the Technical Specifications and the Environmental j

Protection Plan.

i 3.

This license amendtr.ent is effective as of the date of its issuance and enust be fully implemented no later than 30 days from the date of issuance.

I FOR THE NUCLEAR REG LATORY COMMISSION i

George.

Knight Director i

Project Directorate V l

Division of Reactor Projects - III,

!Y, Y and Special Projects I

\\

i

Attachment:

j Changes to the Technical j

Specifications Date of Issuance: October 18, 1988

)

4 m

1

}

j i

4 l

o e

4 ATTACHMENT TO LICENSE AMENDMENT NO. 57 FACILITY OPERATING LICENSE NO. NPF-15 00CKET NO. 50-362 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by ame:dment number and contain targinal lines indicating the area of change.

Also enclosed are the following overleaf pages to the amended pages.

AMENDMENT PAGE OVERLEAF PAGE 6-1 6-la 6-2 6-3 6-4 6 'i 6-8 6-13 6-14 Pages 6-9 and 6-10 are reissued without change.

i ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Station Manager shall be responsible for over til unit operation and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 The Shift Supervisor (or during his absence from the Control Room Area, a designated individual) shall be responsible for the Control Room command function.

A management directive to this effect, signed by the Vice-President of Nuclear Operations shall be reissued to all station Mrsonnel on an annual basis.

_6. 2 ORGANIZATION OFFSITE 6.2.1 Onsite and offsite organizations shall be established for unit operation and corporate management, respectively.

The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant, Lines of authority, responsibility, and comunication shall be a.

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 descrip-tions 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 Station Manager shall be responsible for overall unit safe operation and shall have control over those onsite retivities necessary for safe operation and maintenance of the p': ant, The Vice President, Nuclear Engineering, Safety, and Licensing and c.

the Vice President and Site Manager shall have corporate responsibil-ity for overall plant nuclear safety.

The Vice President and Site Manager shall take any measures needed to ensure acceptable perform-ance of the staff in operating and maintaining the plant to ensure nuclear safety.

The Vice President, Nuclear Engineering Safety and Licensing shall take any measures needed to ensure acceptable performance of the staff in 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.

SAN ONOFRE-UNIT 3 6-1 AMENDMENT NO. 57

b ADMINISTRATIVE CONTROLS UNIT STAFF 6.2.2 The Unit organization shall be as shown in Figure 6.2-2 and:

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 Reactor Operator shall be in the Control Room when fuel is in the reactor.

In addition, while the unit is in MODE 1, 2 3 or 4, at least one licensed Senior Reactor Operator shallbeIntheControlRoomareaidentifiedassuchonTable6.2-1.

A health' physics technician # shall be on site when fuel is in the c.

reactor, d.

All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handlin during this operetion, g who has no other concurrent responsibilities AsiteFireBgigadeofatleast5membersshallbemaintainedonsite e.

at all times.

The Fire Brigade shall not include the Shift Super-visor and the 2 other members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.

'The health physics technician and Fire Brigade composition may be 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 provided immediate action is taken to fill the required positions.

SAN ONOFRE-UNIT 3 6-la AMENDMENT NO. 5 7 l

l

l 3

ADMINISTRATIVE CONTROLS 4

UNIT STAFF (Continued) i f.

Administrative procedures shall be developed and implemented to l

limit the workin functions; e.g.,g hours of unit staff who perform safety-relatedsenior rea[

physicists, auxiliary operators, and key maintenance personnel.

Adequate shift coverage shall be maintained without routine heavy 3

use of overtime.

The objective shall be to have operating personnel work a normal 8-hour day, 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> 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 shut-I down for refueling, major maintenance or major plant modifications, L

on a temporary basis, the following guidelines shall be followed:

[

i 1)

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 /> h

j straight, excluding shift turnover time.

i 2)

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 /> r

i i

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 ti,an 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, all excluding i

shift turnover time.

i 3)

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

4)

Except during extended shutdown periods, the use of overtime i

should be co'sidered on an individual basis and not for the i

entire staff on a shift.

Any deviation from the above guidelines shall be authorized by the f

]

Station Manager, his deputy, the Manager, Operations or higher levels of management, in accordance with established procedures and

(

with documentation cf the basis for granting the deviation. Controls j

shall be included in the procedures such that individual overtime t

i shall be reviewed monthly by the Station Manager or his designee to

{

assure that excessive hours have not been assigned.

Routine deviation l

from the above guidelines is not authorized,

g. The Plant Superintendent (at time of appointment), Shift Superintendents and Control Room Supervisors shall hold a senior reactor operator

license, h e Control Operators and Assistant Control Operators i

l shall hold e 'eactor operator license.

l 4

)

i l

}

)

SAN ONOFRE-UNIT 3 6-2 AMENDHENT NO. 57 l

i

(This page intentionally blank)

SAN ONOFRE-UNIT 3 6-3 AMENDMENT NO. 5 7 1

o, (This page intention:lly blank)

S 9

SAN ONOFRE-UNIT 3 6-4 AMENDMENT NO 57 1

ADMINISTRATIVE CONTROLS 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)

FUNCTION 6.2.3.1 The ISEG sna11 function to examine plant operating characteristics,

)

NRC issuances, industry advisories, Licensee Event Reports and other sources f

of plant design and operating experience information whi>:h may indicate areas for improving plant safety.

COMPOSITION 6.2.3.2 The ISEG shall be composed of at least five dedicated full-time engineers.

Each shall have a Bachelor's Degree in Engineering or Physical Science or equivalent and at least two years professional level experience in l

his field.

Off-duty qualified Shift Technical Advisors may be used to fulfill l

this requirement.

RESPONSIBILITIES 6.2.3.3 The ISEG shall be respontible for maintaining surveillance of plant activities to provide independent verification

• that these activities are performed correctly and that human errors are reduced as much as practical.

AUTHORITY 6.2.3.4 The ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activities or other means of improving plant safety to offsite organization management.

l RECORDS l

6.2.3.5 Records of activities performed by the ISEG shall be prepared, maintained, and farwarded each calendar month to offsite organization management.

l 6.2.4 SHIFT TECHNICAL ADVISOR The Shift Technical Advisor shall provide technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineering and plant analysis with regard to the safe operation of the unit.

The Shift Technical Advisor shall have a Bachelor's Degree or equivalent in a scientific or engineering discipline with specific training in plant design and in the response and analysis of the plant for transients and accidents.

6. 3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit 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 of Regulatory Guide 1.8, September 1975.

" ot responsible for sign-off function.

N SAN ONOFRE-UNIT 3 6-7 AMENDMENT NO. 5 7

ADMINISTRATIVE CONTROLS 6.4 TRAINING

6. 4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Manager, Nuclear Training and shall oest or exceed the requirements and recommendations of Sections 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55 and the supplemental requirements specified in Section A and C of Enclosure 1 of the March 28, 1980 NAC letter to all licensees, and shall include familiarization with relevant industry operational experience identified by the ISEG.

4.5 REVIEV AND AUDIT

_6. 5.1 ONSITE REVIEV Com ITTEE (OSRC)

FUNCTION 6.5.1.1 The Onsite Review Committee shall function to advise the Station Manager on all matters related to nuclear safety.

COMPOSITION

6. 5.1. 2 The Onsite Review Committee shall be composed of the:

Chairman:

Station Manager

> omber:

Deputy Station Manager hember:

Manager, Operations Member:

Manager, Technical Member:

Plant Superintendent SONGS Units 2 and 3 Member:

Supervisor of I&C Member:

Manager, Health Physics Member:

Supervisor of Chemistry Member:

Manager, Maintenance Member:

Supervising Engineer (NS$$. NSS$ Support, Computer, or STA)

Member:

San Diego Gas &g Senior Engineer {}ectric Representative, ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the 05RC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting seabers in 05RC activities at any one time.

( }85 degree in Engineering or Physical Science plus at least four years pro-fessional level experience in his field.

At least one of the four years experience shall be nuclear power plant experience.

SAN ONOFRE-UNIT 3 0-0

ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.1.4 The 0$RC shall meet at least once per calendar month and as convened by the OSRC Chairman or his designated alternate.

QUORUM 6.5.1.5 The minimum quorum of the 05RC necessary for e performance of the 05RC responsibility and authority provisions of these Technical Specifications shall consist of the Chaf ruen or his designated alternate and four members including alternates.

1 RESPONSIBILITIES 9.5.1.6 The Onsite Review Committee shall be responsible for:

Investigation of all violations of the Technical Specifications a.

includi:tg the preparation and forwarding of reports covering evaluation and recomLendations to prevent recurrence to the Nuclear Safety Group (NSG).

b.

Review of events requiring 24-hour written notification to the Commission.

I Review of unit operations to detect potential nuclear safety hazards.

c.

d.

Performance of special reviews, investigations or analyses and reports thereon as requested by the Station Manager or the N5G.

Review and documentation of judgeent concerning prolonged operation in e.

bypass, channel trip, and/or repair of defective protection channels of process variables placed in bypass since the 14,t OSRC meeting.

AUTHORITY I

i 6.5.1.7 The Onsite Review Committee (05RC) shall:

i a.

Render determinations in writing w..h regard to whether or not items considered under 6.5.1.6(a) above constitute unreviewed safety questions.

t b.

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 Manager of Nuclear i

Operations and MSG of disagreement between the 05RC and the Station Manager; however, the Station Managsr shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

]

r i

i j

SAN ONOFRE-UNIT 3 6-9 AMENDMENT NO. 36 l

i ADMINISTRATIVE CONTROLS RECORDS _

6. 5.1. 8 The Onsite Review Committee shall maintain written minutes of each OSRC meeting that, at a minimum, document the results of all OSRC activities performed under the responsibility and authority provisions of these technical specifhations.

Copies shall be provided to the Nuclear Safety Group.

6.5.2 TECHNICAL REVIEW AND CONTROL i

ACTIVITIES L

6.5.2.1 The Station Maanger shall assure that each procedure and program required by Specification L8 and other procedures which affect nuclear safety, and changes thereto, is preparea by a qualified individual / organization. Each such procedure, and changes thareto, shall be uviewed by an individual / group other than the individual / group which prepared the procedure, or changes thereto, but who may be from the same orgs:'zation as the individual / group which prepared the procedure, or changes thereto.

6.5.2.2 Proposed changes to the Appendix "A" Technical Specificatit,05 shall be prepared by a qualified individual / organization.

Iht, preparation of each proposed Technical Specifications change shall be reviewed by an individual /

group other than the individual / group which prepared the proposed changs, but who may be from the same organization as the indiviuual/ group which prepared the proposed change.

ProposN chav s to the Technical Specificetions shall l

be approved by the Station Marc i

6.5.2.3 Proposed modifications to unit nuclear safety-rela *ed structures, systems and components shall be designed by a qualified inNideml/

organization.

Each such modification shall bt reviewed by an individual / group other than the individual /gM up which designed the modification, but who may be from the same organization as the individual / group which designed the modifi-cation.

Proposed modifications to nuclear safety-related structures, systects and components shall be approved prior to implementation by the Station Manager; or by the Manager, Technical as previously designated by the Station Manager, t

6.5.2.4 Individuals responsible for reviews performed in accordance with 6.5.2.1, 6.5.2.2 and 6.5.2.3 shall be members of the station supervisory staf f, previously designsted by the Station Kanager to perform such reviews.

Each such review shall include a determination of whether or not additional, l

l crost a iplinary, review is necessary.

If deemed nerossary, such review l

shal' de,erformed by the approp'iate designated review personnel.

l 6.5.2..

! reposed tests and experiments which affect station nuclear safety i

And are not addressed in the FSAR or Technical Specifications shall be l

reviewed by the Station Manager, the Manager, Technical, the Manager, Opera-l tions, the Manager, Maintenance, the Deputy Station M4 N er or the Manager, Health Physics as previously desigrated by the Station Manager.

l j

6.5.2.6 The station security program, and implamenting procedures, shall be reviewed at least once per 12 months.

Recommended changes shall be approved

[

by the Station Manager and transmitted to the Manager of Nuclear Operations f

l and to the NSG.

I SAN ONOFRE-UNIT 3 6-12 a-.

ADMINISTRATIVE CONTROLS AUDITS 6.5.3.5 Audits of unit activities shall be performed under the cognizance of the NSG.

These audits shall encompass:

a.

The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 fonths.

b.

The performaace, training and qualifications of the entire unit staff at least once per 12 months.

The results of actions taken to correct deficiencies occurring in c.

unit equipment, structures, ;yster.a or method of operation that affect nuclear safety at least once per 6 months.

d.

The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months.

Any other area of unit operation considered appropriate by the e.

Nuclear Safety Group or Manager of Nuclear Operations.

f.

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

g.

An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified off-site licensee personnel or an outside fire protection firm.

h.

An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.

@,THORITY 6.5.3.6 The NSG shall report to and advise offsite organization management on those areas cf responsibility specified in Sections 6.5.3.4 and 6.5.3.5.

RECORDS 6.5.3.7 Records of NSG activities shall be prepared and maintained.

Report of reviews and audits shall be distributed monthly to the Station Manager and to the management positions responsible for the areas audited.

l l

SAN ONOFRE-UNIT 3 6-13 AMENDMENT NO. 57

ADMINISTRATIVE CONTROLS 0.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTADLE OCCURRENCES:

a.

The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.

b.

Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission shall be reviewed by the OSRC and submitted to the NSG and the Manager of Nuclear Operations.

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

a.

The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Manager of Nuclear Operations and the NSG Chairman shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.

A Safety Limit Violation Report shell be~ prepared.

The report shall be reviewed by the OSRC.

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.

c.

The Safety Limit Violation Report shall be submitted to the Commission, the Manager of Nuclear Operations and the NSG within 14 days of the violation.

d.

Critical operation of the unit shall not be resumed until authorized by the Commission.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maint31ned 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.

l d.

Security Plan implementation.

l l

e.

Emergency Plan implementation, f.

Fire Protection Program implementation.

l l

l SAN ONOFRE-UNIT 3 6-14

___ _ _. _ _ _ _