ML20073P294

Proposed Changes to Tech Spec Sections 7.1 & 7.4 Including Administrative & Editorial Revs

ML20073P294
Person / Time
Site:	Fort Saint Vrain
Issue date:	04/07/1983
From:	PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20073P246	List: ML20073P244 ML20073P294
References
NUDOCS 8304250110
Download: ML20073P294 (26)

Text

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ATTACHMENT _1

SUMMARY

OF PROPOSED CHANGES r

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F304250110 830407 PDR ADDCK 05000267 P

t PDR

SUMMARY

OF PROPOSED CHANGES-Section. Description of Change AC 7.1.1 1) Reduced subsection headings from all capital let-ters to only first letter capitalized.

2) Added subsection 2.1. - staff working hour guide-ifnes.

3) Added subsection 3.c. - Technical Adviser qualifi-cations.

L AC 7.1.2 I) Reduced subsection headings from all capital let-ters to only first letters capitalized.

2) Subsection 1 - revised PORC membership.

AC 7.1.3 1) Reduced subsection headings from all capital let-tors to only first letters capitalized.

2) Subsection 2 - revised the title of one NFSC mem-ber.

3) Subsection 7.b.(5) - revised audit frequency of the facility Emergency Pian and implementing pro-cedures.

-4) Subsection 7.b.(6) - revised audit frequency of the facility Security Plan and implementing pro-cedures.

5) Subsection 7.b.(8) - clarified fire protection auditing requirements Figure-7.1-2 Revised to reflect current organization.

AC 7.4.c.3 Revised to reflect current administrative responsi-bilities.

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ATTACHMENT 2 PROPOSED CHANGE!

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- Fort St. Vrain #1 Technical Spacifications Amendment #

Page 7.1-1 7.1 ORGANIZATION, REVIEW AND AUDIT-ADMINISTRATIVE CONTROLS Applicability Applies t& .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 plaqt operational ',afety.

Specification AC 7.1.1 - Organization, Administrative Controls l 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 to, and be directly responsible to, the Manager, Nuclear Production. The Admini strative 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 overall facility operation and in all matters concerning the Plant _ Operations Review Committee (PORC). He shall delegate in writing this responsibility during his absence.

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c. The Technical Advisors shall report to, and be directly responsible to, the Technical / Administrative Services Manager. The Technical Advisors shall maintain inderandence from normal plant operations as necessary to make

objective evaluations of plant conditio"s and to i.

advise ~ or assist plant management 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 Superintencent of Operations.

(2) Review abnormal and emergency procedures.

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

Fort St. Vrain #1 TGchnical Sp@cifications Amendment #

Page-7.1-3 (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.

l 2. Unit Staff 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.

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 5 members shall be maintained on site at all times *. The Fire Brigade shall not include (3) members of the minimum shift

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Fort St. Vrain #1 Technical Specifications Amendment #

Page 7.1-4 crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.

• 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 of Fire Brigade members provided immediate action is taken to restore the Fire Brigade to within the minimum requirements.

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f. The Technical Advisor shall be in the control room vithin one hour after an emergency call. The Technical Advisors shall work a normal day work schedule but'will be placed "on call" after normal working hours.

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

. Fort St. Vrain #1 Technical Specifications Amendment #

Page 7.1-5

-exceed the qualifications of Regulatory Guide 1.8, September, 1975.

l i. Members of the plant staff who perform safety l - related functions (e.g., Senior Reactor Operators, l Reactcr Operators, Auxiliary Operators, Health l Physicists, and key maintenance personnel) should, l to the extent practicable, work an eight-hour day, l 40-hour week, while the plant is operating. In the

-l ever.t that ' unferseen problen.s 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 temporary basis, the following guidelines shall be l followed:

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 l turnover time).

l (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 period, 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 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period, nor l 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).

. Fort St. Vrain #1 Technical Specifications Amendment #

Page 7.1-6 l (4) Except during extended shutdown periods, the

l use of overtime should be considered on an l individual basis and not-for the entire staff ,

l on shift.

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

l . Authorized deviations to the working hour l _

gufdelines shall be documented and available for l Nuclear Regulatory Commission review.

l 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 t

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.

. Fort St. Vrain #1 Technical Specifications Amendment #

Page 7.1-7

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.

l c. The Technical Advisors shall have a bachelor degree .

l or eauivalent in a scientific or engineering ,

l discipline with specific training in plant design l and response and ar,alysis of the plant for l transients and accidents. An initial training and l retraining program for the Technical Advisors shall l be maintained under the direction of the Training l Supervisor. The Technical Advisors shall also l receive training in plant design and layout,

! including the capabilities of instrumentation in l the Control Room.

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. Fort St. Vrain #1 Technical Spc;cifications Amendment #

Page 7.1-8 Specification AC 7.1.2 - Plant Operations Review Committee (PORC), Administrative Controls The organization, responsibilities, and authority of the PORC shall be as follows:

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

Chairman: Station Manager Technical / Administrative Services Manager Radiation Protection Nanager Superintendent of Operations Superintendent of Maintenance Health Physics Supervisor Results Engineering Supervisor Shift Supervisor Training Supervisor Technical Services Engineering Supervisor l Reactor Engineers l Senior Plant Engineers Training Instructor l 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.

l 3. Meeting Frequency The PORC shall meet at least once per calendar month and as convened by the Chairman.

. Fort St. Vrain #1 Technical Specifications Amendment #'

Page 7.1-9 l- 4. Quorum A quorum .shall consist of the Chairman or alternate Chairman, and four members including alternates.

l 5. Responsibilities f

The PORC shall be responsible for:

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a. Review of all procedures required by Technical Specification 7.4 a), b) and c) and changes thereto, and any ether proposed procedures 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.

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e. Investigation of all violations of the Technical Specifications including the preparation and 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.

. Fort St. Vrain #1 Technical Specifications Amendment #

Page 7.1-10

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

g. Review of facility operations to detect potential nuclear safety hazards.

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h. Performance of special reviews, investigations and reports thereon as-requested by the Chairnan of the Nuclear Facility Safety Committee.

i. Review of the Plant Security Plan and implementing procedures and submittal of recommended changes to the Chairman of the Fort St. Vrain Security i

Committee.

. Fort St. Vrain #1 Technical Specifications

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Page 7.1-11

6. Authority The'PORC shall:

a' . Function to advise the Manager, Nuclear Production on all matters that' affect raclese safety. ..

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b. . Recommend to the Marager, Nuclear Production in writing, approval or discpproval cf items  ;

considered under 5.a thrcugh 5.d. above.

c. Render determinatioas in writing with resard to whether er .not each iten considered under 5.a

' through 5.e 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.

l 7. Records

• The PORC shall maintain written minutes of each meeting i

i and copies shall be provided to the Manager, Nuclear

- Production and Chairman of the Fort St. Vrain Nuclear l Facility Safety Committee, i

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. Fort St. Vrain #1 c5 -Technical Spacifications Amendment #

Page 7.1-12 Specification AC 7.1.3 - Nuclear Facility Safety Committee (NFSC), Administrative Controls 2.

The organization, responsibilities, and authority of the NFSC shall be as follows:

-l 1. Function The Nuclear Facility Safety Committee shall function to provide independent review and audit of design 3ted activities in the areas of:

1) Nuclear Power-Plant Operations

2) Nuclear Engineering

3) Chemistry and Radiochemistry

4) Metallurgy

5) Instrumentation and Control I

6) Radiological Safety i- 7) Mechanical and Electrical Engineering

8) Quality Assurance Practices

9) (Other appropriate fields associated with the unique characteristics of the nuclear power plant.)

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. Fort St. Vrain'#1 Technical Specifications Amendment #

Page 7.1-13 l 2. Membership The NFSC shall be composed of the following:

Chairman: Vice President, Electric Production Manager, Nuclear Prodection Division Manager, Nuclear Engineering Division Quality Assurance Manager l Manager, Risk Managen'ent Consultants, as requireo and appointed b/ the Chairman l 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.

l 4. Consultants Consultants shall be utilized as determined by the Chairman, NFSC, to provide expert advice to the NFSC.

. Fort St. Vrain #1 Tcchnical Specifications Amendment #

Page 7.1-14 l 5. Meeting Frequency The NFSC shall meet at least once per calendar quarter during the initial year of facility operation following fuel load _ing and at least once per six months thereafter.

, l 6. Qgorum A quorum of tne NFSC shall censist of the Chairman or-his designated alternate and a majority of the NFSC members including alternates. No more than a minority of tne quorum shall have line responsibilities for operation of the Tacility.

l 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 unre: lawed safety question.

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

question-as defined in Section 50.59, 10CFR.

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. Fort St. Vrain #1 Technical Specifications Amendment #

Page 7.1-15 (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 statutas, codes, regulations,-orders. Technical Specifications, license requirements, or of internal procedures or instructions affecting nuclear safety.

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

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

(9) Reports and meeting minutes of the PORC.

. Fort St. Vrain #1 Technical Specifications Amendment #

Page 7.1-16

._ 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 cccurring 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 Quality Assurance Program to meet the criteria of Appendix "B", 10CFR50, at least once per two years.

l (5) The review of the facility Emergency Plan and l implementing procedures at least every l 12 months by persons who have no direct I responsibility for implementation of the l Emergency Plan.

'.- Fort St. Vrain #1 Technical SpGcifications Amendment # ~

Page 7.1-17 l (6) The review of the facility Security Plan and l implementing procedures at least every l 12 months by individuals independent of both l security. program canagement ar.d personnel who l have. direct respcnsicility for implementaticr.

< l of the Security Plan.

I (7) Any other area of facility operation ,

, considered appropriate by the 4/F50.  ;

l (8) With respect to fire protectior:

l (a) an annual fire orotection a r.d ioss l prevention inspectior ard audit utiliifna l either quclitica off-site licensee l personnel or an outside fire protection l- firm; l (b) a biennial audit of the fire protection l program and implementing procedures; l (c) a triennial fire protection and loss l prevention inspection and audit utilizing l an outside qualified fire consultant.

l 8. Authority The NFSC shall report to and advise the Vice President, Electric Production on those areas of responsibility specified in 7.b.(7) above.

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. Fort St. Vrain #1 Technical Specifications Amendment #

.Page 7.1-18 l 9. Records Records of NFSC activities shall be prepared, approved and distributed e.s indicated below:

a. Minutes of each NFSC meeting shall be prepares, approved and forwarded to the Vice Pres! dent, Electric Production with',n 30 days folicwing 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 l completion of the review.

c. Aadit 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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. < i. Fort St. Vrain #1 Technical Specifications Amendment #

Page 7.1-21 s

, s 7.4 PROCEDURES - ADMINISTRATIVE CONTROLS Applicability Applies to administrative procedures 'which will govern plant operatiens.

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Objective To ensure that written procedures will be maintained to

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. define requ1rements for plant operation.

Ig.i f f eation AC 7.4 - Procedures, Adr.:inistrative Controls

a. Written h':edures o shall be ,establisned, implemented and maintained covering the activities referenced below: -

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'1. The applicable procedures. recommended in Appendix A-of Regulatory Guide 1.33, November, 1972.

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2. Refueling'operatioRs. 1

3. Surveillance and test activities of safety-related

' - equipment. , ,

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Secu'rity Plan implementation.

5. Emergency Plan implementation.

b. Prollidures and administrative policies of a) above, and changes thereto, shall be reviewed by the PORC and approved by the appropriate Manager prior to s '\

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Page 7.4-1

. implementation and reviewed periodically as set forth in Administrative Procedures.

Security Plan procedures, and changes thereto, shall be reviewed by the Plant Operations Review Committee and approved by the designated Plant Security Officer prior to implementation.

Security Plan procedures and changes thereto, shall be reviewed by the Fort St. Vrain Security Committee.

c. Temporary changes to procedures of a) above may be made provided:

1. The intent of the original procedure is not altered.

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2. The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operators License.

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3. The change is documented, reviewed by the PORC and l approved by the appropriate Manager within 14 days of implementation.

j d. Procedures for personnel radiation protection shall be

! prepared consistent with the requirements of 10 CFR l

l Part 20, and shall be approved, maintained, and adhered i

to for all operations involving personnel radiation exposure.

... -t Fort St. Vrain #1 Technical Specifications Amendment #

Page 7.4-2 Respiratory protective equipment shall be provided in accordance with 10 CFR 20.103.

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