ML20155J628

Proposed Tech Specs Concerning Administrative Controls

ML20155J628
Person / Time
Site:	Fort Saint Vrain
Issue date:	10/14/1988
From:	PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20155J619	List: ML20155J616 ML20155J623 ML20155J628
References
TAC-69862, NUDOCS 8810260493
Download: ML20155J628 (27)

Text

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' ForB St. Vrain #1 l Technical SpecificaBions Amendment No. )

Page 7.1-1 l 7.1 ORGANIZATION, REVIEW, AND AUDIT-AOMINISTRATIVE CONTROLS j Applicability j i

Applies to the lines of authority and responsibility for the  ;

i operational safety of the fac1'ity, and the organization for ,

periodic review and audit of facility operation. ,

Objectives l To define the principal lines of au*hority and i

responsibility for providing continuing review, evaluation, .

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j and improvement of the plant operational safety.  !

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l SPECIFICATION AC 7.1.1 - ORGANIZATION, ADMINISTRATIVE  !

i CONTROLS  !

t l 1. RESPONSIBILITY ,

I l l a. The Manager, Nuclear Production and Station Manager l shall be responsible for overall unit operation and  ;

I shall delegate in writing the succession to this '

l l responsibility during his absence, [

i l b. The Shif t Supervisor (or during his absence from the l control room and Shitt Supervisor's office, a t J l designated individual) shall be responsible for the  !

control l l' l room command function. A management j l directive to this effect, signed by the Senior Vice i President, Nuclear Operations shall be reissued to l

f l all station personnel :n an annual basis. t i

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Fcrt St. Vrain #1 Technical Specifications Amendment No.

Page 7.1-2 l 1. ORGANIZATICN I a. Onsite and Of f site Orc.inizations l Onsite and offsite organizations shall be  !

l established for unit operation and corporate f I management, respectively. The onsite and offsite

I organizations shall include the positions for ,

I activities affecting the safety of the nuclear pcwer  ;

l plant. I I

l (1) Lines of authority, responsibility, and j l communit.ation shall be established and defir.ed ,

f l 1 for the highest management levels through I I

l intermediate levels, including all operating '

i j l organization positions. These relationships l shall be documented and updated, as appropriate. l I'

1 l in the form of organization chaats, functional 4

j l descripticns of departmental responsibilities l i

l l and relationships, and job descriptions for key I per mnnel positions, or in equivalent forms of I documentation. These requirements shall be  !

I documented in the FSAR.  !

I I l l (2) The Manager, Nuclear Production and Station  !

1 i l Manager shall be responsible for overall unit j 1

i i safe operatien and shall have control over those l l onsite activities necessary for safe opera: ion l and maintenance of the plant.

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Fort St. Vrain #1 Technical Specifications Amendment No.

Page 7.1-3 l (3) The Senior Vice President, Nuclear Operations l shall have corporate resnorsibility for overall l plant nuclear safety and shall take any measures l neederi to ensure acceptable perforrance of the l staff in operating, caintaining, and providing

! l technical support to the plant to er.sure nuclear '

l safety.

I (4) The Individuals who train the operating staff  :

I and those who carry out health physics and l quality assurance functions may report to the appropriate onsite manager; huwever, they shall I

l have sufficient organizational freedom to ensure L

l their independence f ron. operating preistres. i l b, Unit Staff j

l (1) Each on-duty shift shall be composed of at least A

l the minimum shift crew composition shown in l Table 7.1-1.

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I (2) A licensed operater must be i- tra control room ,

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, I at all times wnun fuel is in the reactor,  !

1 (3) During shutdown and refueling conditions, an i individual (other thar, the Technical Aavisor)

I with a valid R3 (or SRO) license shall be l present in the control room. Curing all other j l conditions, an individual (other than the l l Technical Advisor) with a valid SRO license l shall be prSsent in tre centrol room.

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Fort St. Vrain 01 Techical Specifications Amendment No.

Page 7.1-4 l (4) Ouring the performance nf reactor startup, I reactor shutdown, and recovery from reactor l trip, two licensed ope,ators must be in the l Control room.

l (5) All corr alterations shall be ob3erved and

,1y supervised by either a licensed Senior

..e to r Operator or Senior Reactor Operator l Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

l (6) An operator or technician qualified in radiation -

protection procedures shall be present at the facility at all times that there is fuel on site.

l (7) A site Fire Brigade of at least five members shall be maintained on site at all times *. The l Fire Brigade shall not include 3 members of the I

minimum shift crew necessary for safe shutdown of the unit and any personnel required for other i

essential functions during a fire emergency. j I -

• Fire Brigade ccmposition may be less than the minimum requirements  !

l 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 I action is taken to restore the Fire Brigade to within the minimum requirements.

. Fort St. Vrain #1 i

., Technical Specifications Amendment No.

g Page 7.1 .

l (8) Members of the' plant staff who perform safety related functions (e.g., Senior Reactor Operators, Reactor Operators, Auxiliary:

l l Operators,. Health Physics Technicians, and key a

maintenance personnel) should, to the extent i

practicable, work an eight-hour day, 40-hour

.1 week, while the plant is operating. In the.

l event that unforeseen problems require +

j substantial amounts of overtime to be used, or i during extended periods of shutdown or ,

refueling,-major maintenance or major plant modifications, on a temporary basis, the -

following guidelines shall bt followtid:

l (a) An individual should not be permitted to i 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 j shift turnover time).

i 4 l (b) An individual should not be permitted to '

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) work more than 16 heurs in any 24-hour i period, nor more tha- 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48- l I' ,

hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any (

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seven-day period (all excluding shift l turnover time). <

l l (c) A break of at least 8 hevs should be allowed between work periods 't (including .

shift turnover time).

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Fort St. Vrain #1 Technical Specifications Amendment No.

Page 7.1-6 i

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

l (9) If unusual circumstances arise requiring deviation from the above guidelines, such l deviation shall be authorized by the Manager, l Nuclear Production and Station Manager, his l designee, or higher levels of management, and l with documentation of the basis for granting the l deviation. Controls shall be established such .

l that excessive individua'. overtime hours have I not been assigned. The paramount censideration l in overtime assign,ent shall be that significant l reductions in the effectiveness of operating 1 personnel would be highly unlikely. Routine i deviation from the above guidelines is not l authorized.

Authorized deviations to the working hour guidelines shall be documented and available for I review by the Nuclear Regulatory Commission.

! (10) The Shift Supervisors, and either the Operations i Manager or at least one Superintendent of '

l Operations shall hold a Senior Reactor i Operator's license. The Reactor Operaters shall l hold a Reactor Operator's license.

Fort St. Vrain (11 Technical Specifications Amendment No.

Page 7.1-7

! (11) Except for the Shift Supervisor, the Shift Crew l Comoosition may be one less than the minimum l requirements of Table 7.1-1 for a period of time j 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 o rdar to accommodate I unexpected absence of on-duty shift crew I members, :ovided immediate action is taken to l restore the Shift Crew Composition to within the l minimum requirements of Table 7.1-1. This l provision does not permit ony shift t.rew l position to be unmanned upon shift change due to I an oncoming shift crewman being late or absent.

l This provision also does not exclude the

• I requirement for an SRO licensed individual to be l in the control room at all times other than ti.e l shutdown conditions specified in Table 7.1-1.

l (12) Durirg any absence of the Shift Supervisor from l the control room or Shift Supervisor's office l while the unit is in ' lot, Cold, or Refueling l Shutdown, an individual witn a valid SR0 license i or R0 license shall be designated to assume the

! control room command function, Ouring any l absence of the Shift Supervisor from the control  ;

l l room or Shift Supervisor's office during all I

] other conditions, an individual (other than the l Technical Advisor) with a valid SRO license i shall be designated to assume the control room i

l command function.

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1 Fort St. Vrain #1 Technical Specifications Amendment No.

Page 7.1-8 i I

TABLE 7.1-1

-4INIkUM SHIFT CREW COMP 0SITION l l Number of Individuals Recuired to Fill Position l l l l l l l During Hot, Cold, or l l l Dosition l Refueling Shutdown (a) l All Other Conditions I l I _

l l l I l l l SS (SRO) l 1 l 1 l l 1 I I l SRO j Not Required l 1 l l l 1 l l RO l 1 1 2 (b) l l l l l l E0 l 1 l 1 l l 1 l l l AT l Not Required l 1 l l l l l l TA (c) l 1 l 1 l I l_ l l SS - Shift Supervisor with a Senior Reactor Operator's License SRO - Individual with a Senior Reactor Operator's License RO - Individual with a Reactor Operator's License EO - Equipment Operator AT - Auxiliary Tender l TA - Technical Advisor (on 1-hour call) l l

l NOTES l a. Per Technical Specification definitions, Section 2.0.

b. One of the two Reactor Operators may be an Equipment Operator with a valid R0 license provided that the staffing requirement for Equipment Operators is being met by another individual qualified as an Eauipment Operator.

c. The Technical Advisor shall be scheduled as required by l Specification 7.1.1.3.b.(5).

Fort St. Vrain #1 Technical Specifications Amendment No.

Page 7.1-8a l 3. TECHNICAL ADVISORS l

l The function, responsibilities ard authority of the l Technical Advisors shall be as follows:

1 l a. Function l The Technical Advisors shall function to make objective l evaluations of plant conditions and to advise or assist l

l plant management in correcting conditions that may l compromise safety of operations, i b. Responsibilities l The Technical Advisors are responsible for:

1 (1) Maximizing plant safety during and after accidents, l transients, and emergencies by independently I assessing plant conditions and by providing l technical assistance to mitigate and minimize the l effects of such incidents and make recommenc'ations l to the Operations Manager or the Superintendents of l Operations, l (2) Reviewing abnormal and emergency procedures.

l (3) Assisting the operations staff in applying the l requirements of the Technical Specifications, l (4) Providing evaluation of Licensee Event Reports from l other plants as assigned, and

Fort St. Vrain 01 Technical Specifications Amendment No.

Page 7.1-8 b l (5) Being in the control room within one hour after an i emergency call. The Technical Advisors shall work l on a normal day work schedule, but will be placed l "on call" after normal working hours.

l c. Authority i The Technical Advisors shall report to, and be directly l responsible to, the Systems Engineering Manager. The l Technical Advisors shall maintain independence from l normal plant operations to be objective in their i evaluations.

l 4. UNIT STAFF QUALIFICATIONS l a. The staffing of the plant shall be in accordance with l American National Stand *ds Institute (ANSI) N18.1-1971, i "Selection and Training of Personnel for Nuclear Power l Plants".

I b. Each member of the facility staff shall - t or exceed l the minimum qualifications of ANSI NIS.1-1971 for the l comparable position, exceot for the Radiation Protection l Manager who : hall meet or exceed the qualifications of l Regulatory Guide 1.8, September, 1975.

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Fort St. Vrain #1 Technical Specifications Amendment No.

Page 7.1-8c l 5. TRAINING l a. A retraining and replacement training program for the l facility staff shall be maintained under the direction I of the Nuclear Training Manager and shall meet or exceed l the requirements and recommendations of Section 5.5 of l ANSI N18.1-1971 and Appendix "A" of 10 CFR 55.

l b. A training program for the Fire Brigade shall be l maintained under the direction of the Nuclear Training l Manager and shall meet or exceed the requirements of l Section 27 of the NFPA Code-1975, except fer Fire l Brigade training / drill sessions which shall be held at -

l least once per calendar quarter.

I c. The Technical Advisors shall have a bachelor's degree or  :

l l equivalent in a scientific or engineering discipline 1 l

l with specific training in plant design and response and l analysis of the plant for transients and accidents. An I initial training and retraining program for the l Technical Advisors shall be maintained under the i direction of the Nuclear Training Manager. The l Technical Advisors shall aisc receive training in plant I design and layout, including the capabilities of i l instrumentation and controls in the control com.

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Fort St. Vrain 01 Technical Specifico% ions Amendment No.

Page 7.1-9 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:

l Chairman: Manager, Nuclear Production and Station l Mana;er l Nucleer Support Manager l Superintendent of Chemistry and Radiation Protection j (Radiation Protection Manager)

Superintendent of Operations l Maintenance Department Manager l Systems Engineering Manager i Superintendent of I&C Maintenance l Operations Manager Nuclear Training Manager

2. Alternates An alternate chairman and alternate members, if required, shall be i, pointed in writing by the PORC Chairman to serve .9 the absence of a chairman or a member; however, no more than two alternate members shall participate as voting members in PORC activities at any one time.

Fort St. Vrain #1 Technical Specifications Amendment No.

Page 7.1-10

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

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

5. Re sppn sibil i tie s The PORC shall be responsible for:

a. Review of all procedures required by Technical -

Specification 7.4(a), (b), (c), (d) and changes thereto, and any other proposed procedure or changes i to approved procedures as deter.nined by the Manager, l Nuclear Production and Station Manager to affect nuclear safety.

b. Review of all proposed tests and experiments that affect nuclect safety.

c. keview of 11 proposed changes to the Technical Specifications,

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

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. Fort St. Vrain 01 e

Technical Specifications Amendment No.

Page 7.1-11

e. Investigstion of all violations of the Technical Specifications including the preparation and forwarding of reports covering the evaluation and recommendations to prevent recurrence to the l Manager, Nuclear Production and Station Manager and to the Chairman of the Nuclear Facility Safety Committee.

f. Review of all Reportable Events.

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

h. Performance :f special reviews, investigations, and reports thereon as requested by the Chairman of the Nuclear Facility Safety Committee.

i. Review of the Plant Security Plan and implementing procedures.

J. Review of the plant Radiological Emergency Response Plan and inplementing procedures.

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Fort St. Vrain #1

. Technical Specifications Amendment No.

Page 7.1-11a

6. Authority The PORC shall:

a. Function to advise the Manager, Nuclear Production l and Station Manager on all matters that affect nuclear safety.

I b. Recommend to the Manager, Nuclear Production and l Station Manager 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 -

through 5.e above constitutes an unreviewed safety question,

d. Provide immediate written notification to tne l Manager, Nuclear Production and Station Manager, and the Chairman of NFSC of disagreement between the l PORC and the Manager, Nuclear Production and Station l Manager; however, the Manager, Nuclear Production I and Station Manager shall have responsibility for resolution of such disagreements pursuant to 6 a above.

Fort St. Vrain #1 0 Technical Specifications Amendment No.

Page 7.1-12

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

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 collectisaly have the competence required to review problems in the following areas:

l a. Nuclear Power Plant Operations l

l b. Nuclear Engineering l c. Chemistry and Radiochemistry I d. Metallurgy l

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1. Fort St. Vrain 01

. Technical Specifications Amendment No.

Page 7.1-13 l e. Instrumentation and Control l f. iiadiological Safety I g. Mechanical and Electrical Engineering l h. Quality Assurance Practices i 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 (As appointed - See Step 4) l Manager, Nuclear Licensing and Resource Management Division l Manager, Nuclear Production and Station Manager Manager, Nuclear Engineering Division Manager, Quality Assurance Division Safety and Security Director Consultants, as required, shall be appointed in writing by l the Senior Vice President, Nuclear Operations.

3. Alternates Alternate members, if required, shall be appointed in writing by l the Senior Vice President, Nu": lea- Operations; however, no more than two alternate members shall participate as voting members in NFSC activities at any one time.

Fort St. Vrain 01 Technical Specifications Amendment No.

Page 7.1-14

4. Chairman The Chairman and Alternate Chairman of the NFSC shall be

{ appointed in writing by the Senior Vice President, Euclear Operations and shall serve as members of the NFSC.

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

6. Meeting Frequency 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.

7. Quorum A quorum of the NFSC shall consist of the Chairman or his designated alternate and a majority of the NFSC members including alternates. ih more than a minority of the quorum shall have line responsibilities for operation of the facility.

8. Responsibilities

a. The Nuclear Facility Safety Committee shall review:

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(1) The safety evaluations for safety significant changes to procedures, equipment, or systems

Fort St. Vrain #1 Technical Specifications Amendment No.

Page 7.1-18 personnel or an outside fire protection fi rm; (b) a biennial audit of the fire protection program and implementing procedures; (c) a triennial fire protection and loss prevention inspection and audit utilizing an outside qualified fire consultant.

(9) The Offsite Oose Calculation Manual and Process Control Program and implementing procedures at least once per 24 months.

(10) The Radiological Environmental Monitoring Program and the results thereof at least once per 12 months.

(11) The performance of activities required by the Quality Assurance Program to meet the provisions of Regulatory Guide 1.21 Revision 1, June 1974 and Regulatory Guide 4.1, Revision 1, April 1975, at least once per 12 months.

9. Authority l The NFSC shall report to and advise the Senior Vice President, Nuclear Operations on tnose areas of responsibility specified in 8.a. 8.b and 8.c above.

10. Records Records of NFSC activities shall be prepared, approved, and distributed as indicated below:

I a. Minutes of each NFSC meeting shall be prepared and l forwarded to the Senior Vice President, Nuclear 1 Operations within 30 days following each meeting.

Fort St. Vrain #1 Technical Specifications Amendment No.

Page 7.1-19 l b. After preliminary approval by the Senior Vice l President, Nuclear Operations, the minutes shall be l distributed to all NFSC members, and approved et the l next NFSC meeting.

l c. Reports of reviews encompassed by Section 8.a, l above shall be forwarded to the Senior Vice President, Nuclear Operations, within 30 days following completion of the review.

l d. Audit repo-ts encompassed by Section 8.c, above i shall be forwarded to the Senior Vice President, Nuclear Operations, and to the management positions resporsibla for the areas audited within 30 days after completion of the audit.

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Fort St. Vrain #1 o

Technical Specifications Amendment No.

Page 7.2-1 7.2 SAFETY LIMITS, ADMINISTRATIVE CONTROLS Applicability Applies to the administrative procedures to be followed in the event that a safety limit is exceeded.

Oyectives To define the administrative procedures which will be followed in the event that a safety limit is exceeded.

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Specification AC 7.2 - Action to be Taken if a Safety Limit is Exceeded, ,

Administrative Controls If a safety limit is exceeded, as defined in Specification SL 3.1 and 3.2, the following action shall be taken:

a. The reactor will be shut down imediately and reactor op'erations shall not be resumed until approval is received from the NRC.

b. The safety limit violation chall be reported to thc Commission, -

l the Manager, Nuclear Production and Station Manager, and to the Chairman, NFSC immediately,

c. A Safety Limit Violation Report shall be prepared. The report 1

shall be reviewed by the PORC. This report shall describe (1) appli-cable circumstances preceding the violation, (2) effects of the violation upon facility compenents, systems or structures, and (3) corrective action taken to prevent recurrence.

d. The Safety Limit Violation Report shall be submitted to the Comission, the Chairman, NFSC and the Manager, Nu: lear Production l and Station Manager within ten days of the violation.

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ATTACH.ENT V 3 SIGNIFICANT HAZARDS CONSIDERATION s

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r SIGNIFICANT HA2ARDS CONSIDERATION  !

I. EVALUATION OF CHANGES A. Specification AC 7.1.1 is revised as follows:

Section 1 "RESPONSIBILITY," was added delegating  ;

control room command responsibility and corporate ,

responsibility for overall nuclear plant safety. This l section directly correlates to Section 6.1 of the  !

Westinghouse Standard Technical Specifications (STS), l NUREG-0452.  !

r Section 2.a. On s i t e and Offsite Organization," was ,

added to provide a directive for the establishment and definition of lines of authority, responsibility, and i i communication for onsite and offsite organizations.

! Th9 section directly correlates to Section 6.2.1 of l the STS, as amended by Generic Letter 88-06 for .

I deletion of the organization charts from the Technical l 1

Specifications (Tech. Specs.).

Section 2.b(1) designates on-duty shift minimum shift -

crew composition per Table 7.1-1. This section follows the guidelines of Generic Letter 88-06, and 1 incoroorates the requiretrents of current Section 2.a. ,

Sections 2.b(2,3,4) discuss licensed operator on-shift i requirements. These sections are added to conform to the formattir.g effort of this amendment; and include ,

1 part of the current clarification text following Table  :

{ 7.1-1 and the requirements of current Section 2.b.

Sections 2.b(S,6,7,8,9) are reformatting and editorial l corrections, which incorporate the requirements of .

current Sections 2.c, 2.d. 2.e, 2.1, and the position f titles of the Fort St. Vrsin (FSV) reorganization. l Section 2.b(10) was added to delineate those requiring a Senior Reactor Operator's (SRO) license and tnose ,

requiring a Reactor Operator's (RO) license; and follows the guidelines of Generic Letter 88-06.

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{ Section 2.b(11) discusses shift crew composition and  :

, incorporates the requirements of the current final I l

clarification paragraph following Table 7.1-1, which were not included in proposed Sections 2.b(2,3,4).

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Section 2.b(12) was added to delineate control room command responsiblity in the absence of the Shift Supervisor, and further expounds on proposed Section 1.b.

Tabla 7.1-1 was relocated within Specification AC 7.1.1. The table retains the same requirements as the current Table 7.1-1. However, the page is reformatted to include the appli able notes.

Section 3, "TECHNICAL ADVISORS," is a reform:tting addition. This section incorporates the requitements of current Sections 1.c and 2.f, with position titles per the FSV reorganization.

Section 4, "UNIT STAFF QUALIFICATIONS," is a reformatting addition and incorporates the requirements of current Sections 2.g and 2.h. "Upon commer.ccment of commercial operation" is celeted since this stipulation is not necessary.

Sectior 5, "TRAINING," reformats and incorporates the requirenents of current Section 3. "Compliance with Section 5.5 of ANS! 18.1-1971 shall be schieved no later than 6 months following commencement of -

commercial operation" is deleted since this stipulation is not necessary.

B. Speci fication AC 7.1.2 is revised as follows:

Section 1, Plant Operations Review Committee (PORC)

Membership, is revised to incorporate position titles of the FSV reorganization. No expertise is deleted from the PORC, and the positions meet the description of ANSI N18.1.

Sections S.a, 5.e 6.d and 7 contain a position title change only. Responsibility and expertise remain the same.

Sections 3, 4, 9, and 10 contain position title enange only. Responsibility and expertise remain the same.

Section 5.k. relative to PORC review of every unplanned onsite release of radioactive material to the environs, is deleted. This requirement is considered to be adequately covered in Sections 5.a through S.g. Also, several recent plant Technical Specifications hava been found not to include this requirement: River Bend 1, Grand Gulf 1, Nine Mile Point 2, and Palo Verde 1. Deletion of Section 5.k is also conristent with the Tech. Spec. Upgrade Program draft.

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l C. Specification AC 7.1.3 is revised as follows:

Section 1 contains only formatting changes.

Section 2 contains revisions to the Nuclear Facility Safety Committee (NFSC) Membership relative to position titles per the FSV reorganization. The actual membership and areas of responsibility / expertise remain the same.

Sections 3, 4, and 9 contain a cosition title change only. Responsibility and expertise remain the same.

Section 10.a is revised to delete the requirement that ear.h NFSC meeting's minutes be approved within 30 days following each meeting. Section 10.b was added to direct the preliminary approval of the NFSC meeting minutes by the Senior Vice President, Nuclear Operations. It also directs the distribution of the minutes to the NFSC members, and approval of the minutes at the next NFSC meeting. 1hese revisions will ensure that the entire NFSC membership will be given the opportunity to vot9 on the approval of the minutes of the last NFSC meeting.

D. Paces 7.1-20, 7.1-21. 7.1-22. and 7.1-23 are deleted:

Pages 7.1-20 and 7.1-21 contain Table 7.1-1 and its associated notes and clarification information. All this information is included elsewhere in the proposed amendment.

Pages 7.1-22 and 7.1.23 contain the organization charts (Figures 7.1-1 and 7.1-2). These charts are deleted from the Tech. Specs., based on the recommendation of Generic Letter 88-06.

E. Soecification AC 7.2 is revised as follows:

Sections b. and d. contain a position title cnange only. Responsibility and expertise remain the same.

II. CONCLUSION Except as otherwise noted above, tnis proposed amenomont reformats current Administrative Controls Specification 7.1.1 requirements to cetter conform to STS formatting; deletes organization charts per the guidelines of Generic Letter 88-06; and retitles certain positions in AC 7.1.1, 7.1.2. 7.1.3. and 7.2 to conform to the FSV reorganization oegun May 12, 1933.

r o Based on the above, this proposed change does not

. .invol,ve a significant hazards consideration because operation of FSV in accordance with this change would not: involve a significant increase in the probability or consequences of an accident previously evaluated; create the possibility of a new or different kind of accident from any accident previously evaluated; involve a significant reduction in a margin of safety.

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