ML20069D343

Proposed Tech Specs Re Staff Working Hour Guidelines

ML20069D343
Person / Time
Site:	Fort Saint Vrain
Issue date:	09/14/1982
From:	PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20069D326	List: ML20069D322 ML20069D331 ML20069D343
References
NUDOCS 8209210049
Download: ML20069D343 (17)

Text

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Fort St. Vrain 01

. Technical Specifications.

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,

" Selection 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.

l 1. Members of the plant staff who perform safety-l related functions (e.g., Senior Reactor Operators, l Reactor Operators, Auxiliary Operators, Health I physicists, and key maintenance personnel) should, I to the extent practicable, work an eight-hour day, l 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. In the

] event that unforseen problems require substantial l

amounts of overtime to be used, or during extended l periods of shutdown for refueling, major l maintenance or major plant modifications, on a l l temporary basis, the following guidelines shall be i

l l followed:

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8209210049 820914 p DR ADOCK 05000267 PDR l

port St. Vrain 01 Technical Specifications Amendment #

, Page 7.1-6 l (1) An individual should not be permitted to work l 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 I turnover time).

1 (2) An individual should not be permitted to work l 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 pericd, nor l 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 l (all excluding shift turnover time).

l (3) A break of at least eight hours should be l allowed between work periods (including shift l turnover time).

l (4) Except during extended shutdown periods, the i use of overtime should be considered on an I individual basis and not for the entire staff l on shift.

I If unusual circumstances arise requiring deviation l from the abov9 guidelines, such deviation shall be l authorized by the station manager or his designee, l or higher levels of management. The paramount I consideration in such authorization shall be that l significant reductions in the effectiveness of l operating personnel would be highly unlikely.

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rort St. Vrain 01 Technical Specifications Amendment #-

Page 7.1-7 l Authorized deviations to the working hour l guidelines shall be documented and available for I

l NRC review.

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

b. A training program for the Fire Brigade shall be maintained under the direction of the Training Supervisor and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975, except for Fire Brigade training / drill sessions which shall be held at least once per calendar quarter.

c. An initial training and retraining program for the Technical Advisors shall be maintained under the

fort St. Vrain 01 Technical Specifications Amendment #

Page 7.1-8 direction of the Training Supervisor. The Technical Advisors shall receive specific training in the response and analysis of the plant for transients and accidents. The Technical Advisors shall also receive training in plant design and layout, including the capabilities of instrumentation and controls in the control room.

SPECIFICATION AC 7.1.2 - PLANT OPERATIONS REVIEW COMMITTEE (PORC), ADMINISTRATIVE CONTROLS i

i The organization, retponsibilities, and authority of the PORC shall be as follows:

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

Chairman: Station Manager Technical / Administrative Services Manager Radiation Protection Manager Superintendent of Operations Superintendent of Maintenance Health Physics Supervisor Results Engineering Supervisor

Fort St. Vrain #1 Technical Specifications Amendment #

Page 7.1-9 Shift Supervisor Training Supervisor l Maintenance QC Supervisor l Scheduling / Stores Coordinator Technical Services Engineering Supervisor Senior Maintenance Supervisor Main.tenance Supervisor -

Security Supervisor Reactor Engineer Technical Services Engineer Technical Advisors Training Instructor

2. ALTERNATES An alternate chairman and alternate members, if required, shall be appointed in writing by the PORC Chairman to serve in the absence of a chairman or a .

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

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3. MEETING FRE0VENCY The PORC shall meet at least once per calendar month l

l and as convened by the Chairman.

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Fort St. Vrain 01 Technical Specifications Amendment #

Page 7.1-10

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

5. RESPONSIBILITIES The PORC shall 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 te:ts and experiments that affect nuclear safety.

c. Review of all proposed changes to the Technical -

Specifications.

d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.

e. investigation of all violations of the Technical Specifications including the preparation and 4

1

.inart St. Vrain 01 Technical Specifications Amendment #

Page 7.1-11 forwarding of reports covering the evaluation and recommendations- to prevent recurrence to the 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. Review 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.

Fort St. Vrain 01 Technical Specifications Amendment #

Page 7.1-12

b. Recommend to the Manager, Nuclear Production in writing, approval or disapproval of items considered under 5.a through 5.d, above.

c. Render determinations- in writing with regard to whether or not each item considered under 5.a throagh 5.e above constitutes an unreviewed safety question.

d. Provide immediate written notification to the Manager, Nuclear Product: - and the Chairman of NFSC of disagreement cetween the PORC and the Station Manager; however, the Station Manager shall have responsibility for resolution of such disagreements pursuant to 6.a above.

7. RECORDS 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.

Fort St. Vrain #1 Technical Specifications Amendment #

Page 7.1-13 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 Safety 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.)

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F'rt o St. Vrain 01 Technical Specifications Amendment #

Page 7.1-14

2. MEMBERSHIP The NFSC shall be composed of the following:

Chai rman: Vice President, Electric Production Manager, Nuclear Production Division Manager, Nuclear Engineering Division Quality Assurance Manager l Manager, Risk Management 4

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.

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4. CONSULTANTS

! Consultants shall be utilized as determined by the Chairman, NFSC, to provide expert advice to the NFSC.

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F'rt o St. Vrain 01 Technical Specifications Amerdment #

Page 7.1-15

5. MEETING FREOVENCY The NFSC shall meet at least once per calendar quarter during the initial year of facility operation following fuel loading and at least once per six months thereafter.

6. QUORUM A quorum of the NFSC shall consist of the Chairman or his designated alternate and a majority of the NFSC members including a cernates. 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 I

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Fort St. Vrain 01

. Technical Specifications Amendment #

Page 7.1-16 that such actions did not constitute an unreviewed safety question.

(2) Proposed changes to procedures, equipment or systems which involve an unreviewed safety-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.

(4) Proposed changes in Technical Specifications or licenses.

(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 performance of plant equipment that affect nuclear safety.

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Fort St. Vrain #1 Technical Spacifications Amendment #

Page 7.1-17 (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 in some aspect of design or operation of structures, systems, or components, that affect nuclear safety.

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

b. Audits of facility activities shall be performed ,

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

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

(2) The performance, training, and 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

F~ ort St. Vrain #1 Technical Specifications Amendment #

Page 7.1-18 that affect nuclear safety at least once per six months.

(4) The performance of activities required by the Quality Assurance Program to meet the criteria of Appendix "B", 10CFR50, at least once per

two years.

(5) The facili'ty Emergency Plan and implementing I

procedures at least once per two years.

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

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

(8) An audit of the Fire Protection Program including a fire protection and loss prevention inspection shall be perfo rmed -

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

f This audit must be performed by an outside i

qualified fire consultant at intervals no greater than 3 years.

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F'rt o St. Vrain 01 Technical Specifications Amendment #

. Page 7.1-19

8. AUTHORITY The NFSC shall report to and 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, approved and forwarded to the Vice President, Electric Production within 30 days following each meeting.

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

above shall be forwarded to the Vice President, Electric Production within 30 days following -

completion of the review,

c. Audit reports encompassed by Section 7.b, above shall be forwarded to the Vice President, Electric l

Production and to the management positions responsible for the areas audited within 30 days l

after comoletion of the audit.

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FORT ST. VRAIN NUCLEAR GENERATING STATION ,

ADMINISTRATIVE AND DEPARTMENTAL MANAGEMENT ORGANIZATION CliART PRESIDENT AND CllIEF EXECUTIVE

- 0FFICER SENIOR VICE PRES.

OPERATIONS VICE PRESIDENT NFSC ELECTRIC PRODUCTION MANAGER, PROD., MANAGER, NUCLEAR MANAGER MANAGER, MAINT.

QUALITY ASSURANCE FUELS, AND SERVICI S PRODUCTION

& ENGINEERING MANAGER NUCLEAR ENGINEERING DIVISION DIVISION yp '1 DIVISION __

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PORC FIGURE 7.1-1

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~ jj Technical Specifications Amendment Page 7.1-21

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