ML20071Q695

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Draft Composite for Tech Spec Section AC 7.1 Re Organization,Review & audit-administrative Controls
ML20071Q695
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 12/13/1982
From:
PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20071Q688 List:
References
NUDOCS 8212290405
Download: ML20071Q695 (24)


Text

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ATTACHMENT l DRAFT Composite for Fort St. Vrain Technical Specification Section AC 7.1 8212290405 821213 PDR ADOCK 05000267 P PDR

Fort St. Vrain #1 Technical SpIcificatiens Amendment #

Page 7.1-1 7.1 ORGANIZATION, REVIEW, AND AUDIT-ADMINISTRATIVE CONTROLS Applicability Applies to the lines of authority and responsibility for the operational safety of the facility, and the organization for periodic review and audit of facility operation.

Objectives To define the principal lines of authority and responsibility for providing continuing review, evaluation, and improvement of the plant operational safety.

SPECIFICATION AC 7.1.1 - ORGANIZATION, ADMINISTRATIVE CONTROLS

1. ORGANIZATION The organization and lines of responsibility which govern plant operation shall be as follows:
a. In all matters pertaining to operation and maintenance of the plant and to these Technical Specifications, the Station Manager shall report I

to, and be directly responsible to, the Manager, Nuclear Production. The Administrative and Departmental Management Organization is shown in Figure 7.1-1.

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Fort St. Vrain #1 Technical Specifications Amendment #

Page 7.1-2

b. The Station Manager is directly responsible for 1

overall facility operation and in all matters concerning the Plant Operations Review Committee (PORC). He shall delegate in writing this responsibility during his absence.

c. The Technical Advisors shall report to, and be di rectly responsible to, the Technical / Administrative Services Manager. The Technical Advisors shall maintain independence from normal plant operations as necessary to make cbjective evaluations of plant conditions and to advise or issist plant managemert in correcting conditions that may compromise safety of operations. The Technical Advisors are responsible for:

(1) Maximizing plant safety during and after accidents, transients, and emergencies by independently assessing plant conditions and by providing technical assistance to mitigate and minimize the effects of such incidents and make recommendations to the Superintendent of Operations.

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Fcrt St. Vrain #1 Tcchnical Sp2cifications Amendment #

Page 7.1-3 (2) Review abnormal and emergency procedures.

(3) Assist the cperations staff in applying the requirements of the Technical Specifications.

(4) Provide evaluation of Licensee Event Reports from other plants as assigned.

d. Organization for conduct of operations of the plant is shown in Figure 7.1-2.
2. UNIT STAFF The unit staff shall be as shown on Table 7.1-1 and:
a. A licensed senior operator shall be present on site at all times when there is fuel in the reactor,
b. A licensed operator must be in the Control Room at all times when fuel is in the reactor. During

. reactor startup, shutdown, and recovery from -

reactor trip, two licensed operators must be in the Control Room.

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

Fort St.'Vrain #1

.Tschnical:Sp cifications Amendment #

Page 7.1-4

d. An operator or technician qualified in radiation protection procedures shall be present at the facility at all times that there is fuel on site.
e. A site Fire Brigade of at least five 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 and any personnel required for other essential functions during a fire emergency.

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  • Fire 3rigade composition may be less than the minimum requirements for a period of time not to exceed two hours in order to accomodate unexpected absence of Fire Brigade members provided immediate action is taken to restore the Fire Brigade to within the minimum requirements,
f. The Technical Advisor shall be in the Control Room within one hour after an emergency call. The Technical Advisors shall work on a normal day work schedule, but will be placed "on call" after normal working hours.

I F:rt St. Vrain #1 Technical $picifications Amendment #

Page 7.1-5

g. Upon commencement of commercial operation, the staffing of the plant shall be in accordance with American National Standards Institute N18.1-1971,

" Select.on and Training of Personnel for Nuclear Power Plants."

h. Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable position, except for the Radiation Protection Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September, 1975.

o i Members of the plant staff who perform safety-related functions (e.g., Senior Reactor Operators, Reactor Operators, Auxiliary Operators, Health .

Physicists, and key maintenance personnel) should, to the extent practicable, warh an eight-hour day, 40-hour week, while the plant is operating. In the event that unforseen 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 tempora ry basis, the following guidelines shall be followed:

Fort St. Vrain #1 ,

Technical Specificctions Amendment #-

Page 7.1-6 (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 /> straight (excluding shift  !

, turnover time). l (2) An individual should not be permitted to work f 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 j 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 f (all excluding shift turnover time).  !

(3) A break of at least eight hours should be f i

allowed between work periods (including shift l I

turnover time).

f (4) Except during extended shutdown periods, the j i l

use of overtime should be considered on an  !

i i individual basis and not for the entire staff  !

4 l on shift. I j .

1 If unusual circumstances arise requiring deviation '

i from the above guidelines, such deviation shall be I authorized by the Station Manager or his designee,  !

t I or higher levels of management. The paramount [

i consideration in such authorization shall be that +

I significant reductions in the effectiveness of  !

operating personnel would be highly unlikely. [

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Fcrt St. Vrain #1 Tschnical Sp;cifications

. Amendment #

Page 7.1-7 Authorized deviations to the working hour guidelines shall be documented and available for Nuclear Regulatory Commission review.

3. TRAINING
a. A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Supervisor and shall meet or exceed the requirements and recommendations of I

Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10CFR Part 55. Compliance with Section 5.5 of ANSI 18.1-1971 shall be achieved no later than six months following commencement of comn.ercial operation.

b. A training program for the Fire E'igade shall be maintained under the direction of the Training Supervisor and shall meet or exceed the requirements of Section 27 of the NFFA Code-1975, ,

I except for Fire Brigade training / drill sessions which shall be held at least once per calendar quarter.

c. The Technical Advisors shall have a bachelor degree or equivalent in a scientific or engineering

Fort St. Vrain #1 Technical Sp:cificctions i Amendment #

Page 7.1-8 discipline with specific training in plant design and response and analysis of the plant for transients and accidents. An initial training and retraining program for the Technical Advisors shall be maintained under the direction of the Training Supervisor. The Technical Advisors shall also .

receive training in plant design and layout, including the capabilities of instrumentation in the Control Room.

i SPECIFICATION AC 7.1.2 - PLANT OPERATIONS REVIEW COMMITTEE (PORC), ADMINISTRATIVE CONTROLS The organization, responsibilities, and authority of the PORC shall be as follows:

1. MEMBERSHIP The Plant Operations Review Committee shall be composed of the following:

Chairman: Station Manager Technical / Administrative Services Manager f

Radiation Protection Manager i

Superintendent of Operations Superintend -t of Maintenance i Health Physics Supervisor L___.

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Fort St. Vrain #1

' Technical Spscificaticns i Amendment #

l Page 7.1-9 i

! Results Engineering Supervisor I Shift Supervisor Training Supervisor

Maintenance QC Supervisor i

Scheduling / Stores Coordinator Technical Services Engineering Supervisor Senior Maintenan:e Supervisor Maintenance Supervisor i

Security Supervisor Reactor Engineer 4

Technical Services Engineer i

Technical Advisors Training Instructor i
2. ALTERNATES An alternate chairman and alternate members, if I

required, shall be appointed in writing by the PORC l Chairman to serve in the absence of a chairman or a

! member; however, no more than two alternate members l shall participate in PORC activities at any one time.

3. MEETING FREQUENCY I ,

l The PORC shall meet at least once per calendar month ,

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and as convened by the Chairman.

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Fsrt St. Vrain #1  !

Tcchnical Sp;cifications j

Amendment #  !

Page 7.1-10 l

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4. QUORUM A quorum shall consist of the Chairman or alternate Chairman, and four members including alternates.

5.

RESPONSIBILITIES The PORC sFall be responsible for:

a. Review of all procedures required by Technical Specification 7.4(a), (b), and (c) and changes thereto, and any other proposed procedure or changes to approved procedures as determined by the Station 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.
d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety, i

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e. Investigation of all violations of the Technical Specifications including the pre paration and forwa rding of reports covering the evaluation and recommendations to prevent recurrence to the

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Fort St. Vrain #1 Tcchnical Specificaticns Amendment #

Page 7.1-13 L

SPECIFICATION AC 7.1.3 - NUCLEAR FACILITY SAFETY COMMITTEE (NFSC), ADMINISTRATIVE CONTROLS The organization, responsibilities, and authority of the NFSC shall be as follows:

1. FUNCTION The Nuclear Facility Satety Committee 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
d. Metallurgy
e. Instrumentation and Control
f. Radiological Safety
g. Mechanical and Electrical Engineering
h. Quality Assurance Practices
1. (Other appropriate fields associated with the unique characteristics of the nuclear power plant.)
2. MEMBERSHIP The NFSC shall be composed of the following:

Chairman: Vice President, Electric Production Manager, Nuclear Production Division

Fcrt St. Vrain #1 TGchnical Spscifications Amendment #

Page 7.1-14 Manager, Nuclear Engineering Division Quality Assurance Manager Manager, Risk Management Consultants, as required and appointed by the Chairman

3. ALTERNATES An alternate chairman and alternate members, if required, shall be appointed in writing by the Chairman; however, no more than two alternate members shall participate in NFSC activities at any one time.
4. CONSULTANTS Consultants shall be utilized as determined by the Chairman, NFSC, to provide expert advice to the NFSC.
5. MEETING FREQUENCY The NFSC shall meet at least once per calendt quarter j during the initial year of facility operation following

.,. fuel loading and at least once per six months thereafter.

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6. QUORUM A quorum of the NFSC shall consist of the Chairman or his designated alternate and a majority of the NFSC 4

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Fort St. Vrain #1 TGehnical Specifications Amendment #

Page 7.1-15 members including alternates. No more than a minority of the quorum shall have line responsibilities for operation of the facility.

7. RESPONSIBILITIES
a. The Nuclear Facility Safety Committee shall review:

(1) The safety evaluations for changes to procedures, equipment, or systems affecting nuclear safety and tests or experiments affecting nuclear safety completed under the provision of Section 50.59, 10CFR, to verify that such actions did not constitute an unreviewed safety question.

(2) Proposed changes to procedures, equipment, or

systems which involve an unreviewed safety 4

question as defined in Section 50.59, 10CFR.

(3) Proposed tests or experiments which involve an unreviewed safety question, as defined in Section 50.59, 10CFR. 1 (4) Proposed changes in Technical Specifications or licenses.

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Fort St. Vrain #1 Tcchnical SpIcifications Amendment #

Page 7.1-16 (5) Violation of applicable statutes, codes, regulations,-orders, Technical Specifications, license requirements, or of internal

! procedures or instructions affecting nuclear safety.

(6) Significant operating abnormalities or deviations from normal and expected

t performance of plant equipment that affect nuclear safety.

(7) All events which are required by regulations or Technical Specifications to be reported to the NRC in writing within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(8) Any indication that there may be a deficiency l

in some aspect of design or operation of structures, systems, or components, that affect nuclear safety.

(9) Reports and meeting minutes of the PORC. l l

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b. Audits of facility activities shall be performed j l

l under the cognizance of the Nuclear Facility Safety l Committee. These audits shall encompass:

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i F:rt St. Vrain #1 Technical Specifications Amendment #  ;

Page 7.1-17_ i

.(1) The conformance of facility operation to all provisions contained withir, the Technical Specifications and applicable license conditions at least once per year.

(2) The performance, training, ar.d qualifications, of the facility staff at least once per year.

(3) The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems, or method of operation that affect nuclear safety at least once per six months.

(4) The performance of activities required by the j Quality Assurance Program to meet the criteria i

of Appendix "B", 10CFR50, at least once per two years.

i (5) The facility Emergency Plan and implementing procedures at least once per two years.

l (6) The facility Security Plan and implementing procedures at least once per two years, t

1 (7) Any other area of facility operation considered appropriate by the NFSC.

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Fcrt St. Vrain #1 Technical Sp;cifications Amendment #

Page 7.1-18 (8) An audit of the Fire . Protection Program including a fire protection and loss prevention inspection shall be performed f

annually, utilizing qualified off site licensee personnel, an outside fire protection firm, or an outside qualified fire consultant.

This audit must be performed by an outside qualified fire consultant at intervals no greater than three years.

8. AUTHORITY

! The NFSC shall report to ar.d advise the Vice President, Electric Production on those areas of responsibility

, specified in b.(7) above.

9. RECORDS
Records of NFSC activities shall be prepared, approved, and distributed as indicated below
a. Minutes of each NFSC meeting shall be prepared, 1

- approved, and forwarded to the Vice President, Electric Production within 30 days following each meeting.

b. Reports of reviews encompassed by Section 7.a, 1

, above shall be forwarded to the Vice President, i

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Page 7.1-19 Electric Production within 30 days following l

completion of the review.

c. Audit reports encompassed by Section 7.b, above shall be forwarded to the Vice President, Electric Production and to the management positions responsible for the areas audited within 30 days after completion of the audit.

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. Fort St. Vrain #1 Technical Sp;cificatiens Amendment # .

Page 7.1-20 TABLE 7.1-1 MINIMUM SHIFT CREW COMPOSITION (

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l l l l l Number of Individuals Required to Fill Position l t l l During Hot, Cold, or l l l Position l Refueling Shutdown (a) l All Other Conditions l l i l l l SS (SRO) l 1 l 1 1 I I I I  :

I SRO l Not Required l 1 l 1 1 I I I i l R0 1 1 l 2 (b) l i I I I I i l E0 l 1 l 1 l  !

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l AT Not Required l i 1 l I I I I l TA (c) l 1 l 1 l [

t SS - Shift Supervisor with a Senior Reactor Operator's License i SRO - Individual with a Senior Reactor Operator's License .

RO - Individual with a Reactor Operator's License l

- EO - Equipment Operator i 1 AT - Auxiliary Tender i TA - Technical Advisor  !

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In addition to the requirements of Section 7.1.1(2), the following  ?

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apply: l, 4

During hot shutdown, cold shutdown, or refueling shutdown [

conditions, an individual (other than the Technical Advisor) with

-a valid R0 (or SRO) license shall be present in the Control Room. f t

. During all other conditions, an individual (other than the  !

l Technical Advisor) with a valid SRO license shall be present in  ;

the Control Room.

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Fort St. Vrain #1 Technical Sp:cificaticns Amendment #

Page 7.1-21 Except for the Shift Supervisor, the Shift Crew Composition may be one less than the minimum requirements of Table 7.1-1 for a period of time not to exceed two hours in order to accomodate unexpected absence of on-duty shift crew members, provided immediate action is taken to restore the Shift Crew Composition to within the minimum requirements of Table 7.1-1. This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewmas being late or absent. This provision also does not exclude the requirement for an SRO licensed individual to be in the Control Room at all times other than the shutdown conditions specified in Table 7.1-1.

NOTES: (a) Per Technical Specification definitions, Section 2.0.

(b) One of these two Reactor Operators may be an Equipment

] Operator with a valid R0 license.

(c) The . Technical Advisor shall be scheduled as required by Specification 7.1.1(2)(f).

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FORT ST. VRAIN tluCLEAR GENERATING STATION . , i i

j Al>HINISTitATIVE AND DEPARTilENTAL HANAGEHENT ORGANIZATION CilART i PRESIDENT AND I CilIEF EXECUTIVE 1 0FFICER (

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MANAGER, PROD., HANAGER HUCLEAR HAHAGER HANAGER, HAINT.

QUALITY ASSURANCE FUELS, AND SERVICES PRODUCTION NUCLEA!! ENGINEERIM & ENGINEERING j HANAGER DIVISION DIVISION DIVISION

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) Sr. Maint. Resulto Training Shift Water Health Cler: Leal Security sched/ g gg,,,gg,g Supervisor Engineerin i Supervisor Supervisor Chemist Physica Supervisor Supervisor Storee/qC S e rvi e r Supervisor Supervisor Q 1/ shift p Supervisor

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j _ Supervisor Operator Operator Tender Physicist Radio Advisors Services Engineer Sagineer j 2/ shift 2/shiftg 2/ shift Cheelet i 3

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  • Either the Station Manager or the Superintendent of Operatione shall posoees a senior license.

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-Tcchnical Sp:cificaticns.

Amendment #

Page 7.1-12

c. Render determinations in writing with regard to whether or not each item considered under 5.a through 5.3 above constitutes an unreviewed safety question.
d. Provide immediate written notification to the Manager, Nuclear Production and the Chairman of NFSC of disagreement between the PORC and the Station Manager; however, the Station Manager shall have responsibility for resolution of such disagreements pursuant to 6.a above.

j 7. RECORDS i The PORC shall maintain written minutes of each meeting and copies shall be provided to the Manager, Nuclear Production and Chairman of the Fort St. Vrain Nuclear Facility Safety Committee.

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Fcrt St. Vrain #1 Technical Sp;cifications Amendment #

Page 7.1-11 Manager, Nuclear Production and to the Chairman of the Nuclear Facility Safety Committee.

f. Review of events requiring 24-hour notification to the Commission,
g. Re,lew of facility operations to detect potential nuclear safety hazards.
h. Performance of special reviews, investigations, and reports thereon as requested by the Chairman of the Nuclear Facility Safety Committee.
1. Review of the Plant Security Plan and implementing procedures and submittal of recommended changes to the Chairman of the Fort St. Vrain Security Committee.
6. AUTHORITY The PORC shall:
a. Function to advise the Manager, Nuclear Production on all matters that affect nuclear safety.
b. Recommend to the Manager, Nuclear Production in writing, approval or disapproval of items considered under 5.a through 5.d, above.

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