ML20248D646

Amend 69 to License DPR-34,changing Tech Spec Section 7 Re Administrative Controls

ML20248D646
Person / Time
Site:	Fort Saint Vrain
Issue date:	03/31/1989
From:	Calvo J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20248D642	List: ML20248D638 ML20248D646 ML20248D650
References
NUDOCS 8904110528
Download: ML20248D646 (24)

Text

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'.- -d UNITED STATES

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[ ' e, f g NUCLEAR REGULATORY COMMISSION

$' 'E: WASHINGTON, D. C. 20555 n . ).

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'pUBLIC SERVICE COMPANY OF. COLORADO DOCKET NO. 50-267  !

l FORT ST. VRAIN NUCLEAR GENERATING. STATION 4 l l AMENDMENT TO FACILITY OPERATING LICENSE.

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. Amendment No.69- I License No. DpR-34 l

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

~A. The application for amendment by Public Service Company of- '

Colorado (the licensee) dated October'14, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set l

forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance: (1) that the activities authorized by. this amendraent can be conducted without- endangering the health and safety of the public, and (ii) that such activities kill be conducted in compliance with the Comission's regulations; l

D. The issuance of this license amendment will not be' inimical to the comon defense and security or to the health and safety of the public; and l

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

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8904110528 890331 p

{DR ADOCK 05000029 PDC

2 I 2. Accordingly, the license is amended by changes to the Technical Specificaticas as indicated in the attachrnent to this . license amendment, ar.d paragraph 2.D.(2) of Facility Operating License No. DPR-34 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specific 9tions contained in Appendices A and B, as revised thr.ough Amendrnent No. 69, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. The license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION da l w lw' G .

Jose A. Calvo, Director t ,

Project Directorate - IV Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: March 31, 1989

ATTACHMENT TO LICENSE AMENDMENT NO.69 TO FACILITY OPERATING LICENSE NO. DPR-34 DOCKET NO. 50-267 heplace the following pages of the Appendix A' Technical Specifications with the att6ched pages as indicated. The revised pages are identified by amendaent number- and contain vertical lines indicating the areas of change.

Remove- Insert 7.1-1 7.1-1 7.1-2. 7.1-2 7.1-3 7.1-3 7.1-4 7.1-4 7.1-5 7.1-5 7.1-6 7.1-6.

7.1-7 7.1-7 l 7.1-8 7.1-8 )

7.1-Ba j 7.1-8b  ;

7.1-8c 7.1-9 7.1-9 7.1-10 7.1-10 7.1-11 7.1-11 7.1-11a 7.1-12 7.1-12 7.1-13 7.1-13 7.1-14 7.1-14 7.1-18 7.1-18 7.1-19 7.1-19 7.1-20 -

7.1-21 -

7.1-22 -

7.1-23 -

7.2-1 7.2-1

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Fort St. Vrain #1 Technical Specifications-Amendment No. 36,69 I Page 7.1-1 17.1 ORGANIZATION,' REVIEW. AND AUDIT-ADMINISTRATIVE CONTROLS Aeolicability

> Aoplies 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. \

l Obiectives To define the principal- lines. of . authority and l responsibility for providing cor.tinuing review, evaluation.

and improvement of the plant operational safety.

SPECIFICATION AC 7.1.1 -

ORGANIZATION, ADMINISTRATIVE

.i CCNTROLS i

l l 1. REsc0NSIBILITY' l

I I a. The Manager, Nuclear Production'and Station Manager I shall be responsible for overall unit operation and i shall delegate in writing the succession to this

'l responsibility during his absence. >

1 b. The Shift Supervisor (or during his absence from the I control room and Shift Supervisor's office, a

1. cesignated individual) shall be responsible for the I control room command function. A management l directive to this effect, signed by the Senior Vice 1

l President, Nuclear Operations shall be reissued to, i all station personnel on an annual basis.

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Fort St. Vrain #1 Technical Specifications Amendment No. M ,59 - 1 Page 7.1-2

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1 2. ORGANIZATION I a. Onsite ar.c Offsite Greanizations l Onsite. and offsite organizations shall' be

.1 established- for unit eperation and corporate;

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l management, respectively. The onsite and offsite I organizations shall include the positions for l l activities affecting the safety of the nuclear power I plant, 4

I (1) Lines of authority, responsibility, and I

communication shall be established and defined

. 1 l for. the- highest management levels through I intermediate levels, including all operating 1

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

l in the form of organization charts, functional l

l descriptions of depa rtmental responsibilities l and' relationships, and job descriptions for key l personnel positions, or in equivalent forms of I documentation. These requirements shall be I documented in the FSAR.

1 (2) The Manager, Nuclear Production and Station l Manager shall be responsible for overall unit j

safe operation and shall have control'over those i onsite activities necessary for safe operation l and maintenance of the plant.

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Fort St. Vrain #1 Technical Specifications-

. Amendment.No. 26,69 l Page 7.1-3  !

t (3) The Senior Vice President, Nuclear Operations i shall have-corporate respons'ibility for overall

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!- 1 plant nuclear safety and shall take any measures j 1

needed to ensure acceptable performance of the j l staff in operating,-maintaining, and providing i technical support to the plant to' ensure nuclear J. safety. 1

( (4) The individuals who -train the' operating staff  :

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-l and those who carry out health physics.-and l 1

l Quality assurance functions. may report to the 'l

.I l appropriate onsite manager; however, they shall' j l have sufficient organizational freedom to ensure i their independence from operating pressures.

I b. Unit Staff L

1 i (1) Each on-duty shift shall be composed of at least j l the minimum shift crew composition shown in 1

1 Table 7.1-1. 1 l

l (2) A licensed operator must be.in the control room i

l at all times when fuel is in the recctor.

I (3) During shutdown and refueling conditions...an I

individual (other than the Technical Advisor)

I with a valid R0 (or SRO) license shall be l present in the control room. During all other l l conditions, an individual (other than the i

Technical Advisor) with a valid SRO license l Shall be present in the control room.

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l Fort St. Vrain #1 Technical Specifications Amendment No. 36,69 Page 7.1-4 l (4) During the performance of reactor startup, I reactor shutdown, and recovery from reactor i trip, two licensed operators must be in the l control room.

i (5) All core alterations shall be observed and directly superviseo by either a licensed Senior Reactor Operator or Senior Reactor Operator l [ Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

l i I (6) An operator or technician qualified in radiation 1

protection procedures shall be present at the j

facility at all times that there is fuel on site.

l (7) A site Fire Brigace of at least five members shall be maintained on site at all times

• The l Fire Brigade shall not include 3 memoers of the minimum shif t 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 Brigace composition may be less than the minimum requirements I for a perio: 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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• Technical Specifi AmendmentNo.Megtions l

Page 7.1-5 )

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l (8) Members of the plant staff.who perform safety:

related functions (e.g., Senior Reactor. l l

Operators, Reactor Operators, Auxiliary I

.l Operators, Health Pnysics Technicians, 'and' key maintenance personnel) should, to the extent l practicable, work an .eight-hour day, 40-hour O week, while 'the ' plant is operating. In the f

event that unforeseen problems req ui re .- 1 substantial amounts of overtime to be used, or I during extended periods of shutdown' or l

refueling, major maintenance or major plant' 1 modifications, on a temporary basis, the -

following guidelines shall be followed:

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l (a) 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).

I (b) An individual should- not br permitted to

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work 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' hours in any 48-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 ,

seven-day period - ( a'l l excluding shift t turnover time). i l (c) A break of at- least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between wer . periods. (including shift turnover time).

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Fort St. Vrain #11 Technical Soecificatio'ns

,. 1 Amendment No, M,69 l Pagec7.1-6 ~l 1

a 1 (d) Except during extended shutdown' periods, thel

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~ use of overtime.should be-considered on an-individual basis and not for'.the entire t staff on shift. j

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i (9)-If unusual circumstances. arise- requiring' 1

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deviation frorr : the above guidelines,- such l deviation shall be authorized.by the Manager, j l Nuclear -Procuction and Station Manager,- his cesignee, or higher . levels of management, and

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I I with documentation of the basis. for granting the I deviation. Controls shall be established'such I

that excessive individual- overtime hours have i not been assigned. The paramount consideration l in overtime assignment shall be that significant i

reductions in the effectiveness of operating-l personnel would be highly unlikely. Routine i deviation from the above guidelines is not I authorized.

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

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I (10) The Shift Supervisors, and either the Operations l Manager or at least .one Superintendent of I Operations shall hold a Senior Reactor l Operator's license. The Reactor Operators shall I hold a Reactor Operator's license.

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,e j Fort St. Vrain #1-Technical Specifications f Amendment No, ;E,EE,53,69. i Page 7.1-7 j r

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[ (11) Except for the Shift Supervisor, the Shift Crew 4

! Composition may be one. less than the minimum j

i . requirements of Table 7.1-1 for a period of time-not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order' to' ac'commodate I unexpected absence of on-duty. shift crew l

I members, provided immediate action is taken to I restore the. Shift Crew Composition to within the~

l minimum requirements of Table 7.1-1. This I provision does not permit .any shift crew l

' 1 position to be unmanned upon shift enange due to i

an oncoming shift crewman being late or absent.

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l This provision also does not exclude the

{ requirement for an SRO licensed individual.to be i

in the control room at all times other than the shutdown conditions spetified in Table 7.1-1.

l l (12) During any absence of the Shift Supervisor from I the control room er Shift ' Supervisor's office i while the unit is in Hot, Cold, or Refueling l Shutdown, an individual witn a. valid SRO license 1 or RO license shail be designated to assume tne I control room command function. 'During - any.

t l absence of the Shift Supervisor from the control l l

room or Shift 'Supeivisor's office during all l

l other conditions, an individual (other than the j

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Technical Adv'sor) with a valid SRO license i shall be designateti to assume the control room I command l unction. '

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i J. Fort St. Vrain #1 .

Technical Specifications Amendment.No. Jg,gg,63,69 j Page 7.1-8

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TABLE 7.1-1 1 MINIMUM SHIFT CREW COMPOSITION L

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l Numoer of Individuals Reouired to Fill Position l j l l l l l

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-l During Hot, Cold, or- l l l Position- l Refueling Shutdown (a) l All Other Conditions l-l.

l l- a I l 1 -l l SS (SRO) l 1 l 1,

[

l l  ! l l SRO l Not Required I 1

' l c I I l l RO l-I l 1 l 2 (b) l '.

i i l l i EO l 1 1 l l t i I I l AT l Not Required l 1 l l l- l l l TA (c) l 1 l 1 j l I l' l-SS -

Snift Supervisor with a Senior Reactor Operator's License '

SRO - Individual with a Senior Reactor Operator's License RO - Indivicual with a Reactor Operator's License 5 EO - Ecuipment Operator AT - Auxiliary Tender l

l-TA - Tecnnical Advisor (on 1-hour call)

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l l NOTES l

l a. Per Technical Specification definitions, Section 2.0.

b. One of the two' Reactor Operators may be: an Eauipment i 1

Operator with a valid R0 license provided that the staf fing  !

requirement for Equipment Operators is being met by anothe' l

L indivicual qualified as an Equipment Operator.  ;

c. The. Technical Advisor shal.1 be scheduled as required by I l Specification 7.1.1.3.b.(S).

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Fort St. Vrain #1 1 Technical Specifications .l Amendment No. 69 Page 7.1-Sa l

[ 3. TECHNICAL ADVISORS .J

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}- The function, responsibilities' and authority -of the.

l Technical Advisors shall be'as.'follows:

l' a. Eunction '

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l The ' Tecnnical Advisors shall function to make objective-i 1 evaluations of plant conditions and to advise or assist

l. plant managements in correcting conditions that may l l compromise safe *.y of. operations.

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l b; Responsibilities 1 The Technical Advisors are responsible for:

I (1) Maximi:ing plant safety during and after accidents, l transients, and emergencies 'by independently 1 assessing plant conditions and by providing  ;

l technical assistance to mitigate and minimile the i

effects of such incidents and make recommendations l l to the Operations Manager or the Superintendents of '

I Operations, I (2) Reviewing abnormal and emergency procedures,

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(3) Assisting the operations staff in applying the I

requirements of the Technical Specifications, 1

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.(4) Providing evaluation of Licensee Event Reports from

l. other plants as assigned, and .

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o Feit St. Vrain #1-Tcchnical Specifications

. Amenoment No.69 Page 7.1-8 b n- ,

l .- ( 5) . Bei ng' sin' the control room within' one hour af ter an l- emergency. call. The Technical Advisors shall work ~

I on a normal day work schedule, but.will'be placed i "on call'.' af ter nor' t1 working hours.

l C. Authority 1 The '. Technical Advisors shell report to, and.be~directly I responsible to, the Systems.. Engineering ' Manager. The l l Technical'~ Advisors shall. maintain-' independence 'from

! nermal ' plant operations-'to be ' objective - i n '. their l -evaluations.

I l 4. UNIT STAFF QUALIFICATIONS I a. The staffing of the plant shall be in accordance with i

American National Standards Institute (ANSI) N18.1-1971, I " Selection and Training of Personnel for Nuclear Power l Plants".

I b. Ea

h member of the facility staff shall meet or exceed 1

l' the minimum' qualifications of ANSI N18.1-1971 for the

!' I comparable position, except for the Radiation Protection l

Manager who shall meet or exceed the Qualifications of

'l Regulatory Guide.l.8., September, 1975.

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Technical Specifications Amendnent No. 69 f 1

Page 7,1-8c : -

l, 5. TRAINING 1

l a. A retraining and replacement training. program for tne j l facility staff shall be maintained under the dire: tion

'cf the Nuclear Training Manager and shall meet or exceed

, I the requirements and recommendations of-Sectior 5.5 of' l- ANSI N18.1-1971 and Appendix "A" of 10 CFR 55.

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'l b. A training program' for the Fire Brigade shallbe  !

.1 i maintained uncer the direction of the Nuclear -Training 2 l

Manager and shall meet o 0xceed the requirements of l-Section 27 of the NFPA Code-1975, except for Fire l Brigade . training / drill sessions which shall be held at l least once per calencar cuarter.

I c.

The Technical Advisors shall hava e bachelor's degree or i

eauivalent in a scientific. or engineering discipline-l with specific training in plant design and response and  !

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analysis of the plant for transients and accidents. An l initial training and retraining program for the i

Tecnnical' Advisors shall be maintained u

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-1 direction of the Nuclear Training Manc , The  ;

I Technical Advisors shall'also receive training in plant f

l- 'cesign and layout,- including the capabilities of i

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instrumentation and controls in.the control. room.

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Fort St,'Vrain #1 Technical Specifications

. Amendment No.-35,E5,63,69 Page 7.1-9 I

l Specification AC 7.1.2 Plant' Doerations Review Committee- .J l

(p0RC). Administrative ' Controls

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, Tne organization, responsibilities,.'and authority of the '

PORC sna11 be as follows: 1 1

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

l Chairman: Manager, Nuclear Production and Station l Manager 5

',' Nuclear Support Manager l Superintendent cf~ Chemistry and Radiation Protection {'

l (Raciation Protection Manager)

Superintendent of Operations J Maintenance Department Manager 1 ' Systems Engineering Manager l l Superintendent of I&C' Maintenance <

l Operations Manager Nuclear Training Manager 3

2. Alternates '

An alternate chairman and alternate members, i f.  !

i required, shall be appointed in writing by the PORC i Chairman to serve in 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.

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3 Fort"St. Vrain #1 1 Technical Specifications I Amendment No. M,63.69 -

Page 7.1-10

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3. MeetIno Frecuency 1

Tne PORC sha'l meet at .least once per calendar month and i I

as convened by the Chairman'or.his designated alternate. -

l 4 Ouorum A cuorum shall consist of the Chairman or alternate Chairman, and four members including alternates.

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5. Responsibilities The FORC 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-determined by the Manager, l

Nuclear Production and Station Manager to affect nuclear safety.

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t. 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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. .c Fort St. Vrtin #1 Technical' Specifications 4 Amenoment Nr. 37,5f,69 r Page 7.1 ! i

.e, investigation: of all violations of the Technical Specifications including the preparation. and  !

forwerding '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.

Comr.ittee.

f. Review of all Reportable Events.

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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.

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i. Review of the Plant Security Plan and implementing 1

pror.edures.

J. Review of the plant Radiological Emergency Response '

Plan and implementing procedures.

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Fort St. Vrain #1 Tecnnical Specifications Amendment No.69 Page 7.1-11a L

6. Authcrity Tne PORC shall:

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

l' 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. '

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c. Render determinations in writing with regard to whetner c- not' each item considered under 5.a -

1 through 5.e above constitutes.an unreviewed safety' I l question.

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d. Provide immediate written notification to the 1 Manager, Nuclear Production and Strtion Manager, and-the Chairman of NFSC of disagreement'between.the s

l PORC and the Manager. Nuclear Production and Station l Manager; however, the Manager, Nuclear Production

l. and Station Manager shall have responsibility- for ,

resolution of such d'.sagreements pursuant to 6.a above.

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p Fort St. Vrain #1-Techrical Specifications Amendment'No,' M . M . 69 Page 7.1-12

7. Records l.

The PORC shall maintain written minutes of each meeting a

l and copies shall be provided -to the Manager, Nuclear 1

l Production and Station Manager, and Chairman of the Fort l St. Vrain Nuclear Facility Safety Committee. cl o

Specification AC 7.1.3 - Nuclear Facility' Safety Committee-l l

(NFSC) Administrative Controls-The. organization, res!.onsibilities., and authority of the NFSC snall be as follows:

1 Function -

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The Nuclear Facility Safety Committee shall collectively have the competence required t0' review problems in the following areas:

I a. Nu: lear Power Plant Operations i b. Nuclear Engineering I c. Cnemistry and Radiochemistry

.1 d. Metallurgy i

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Fort St. Vrain #1 Technical Specifications Amendment No, M ,JE.$/,69 Page 7.1-13 1 e. - Instrumentation 1and Control I f Radio. logical Safety.

I g. Mechanical and Electrical Engineering l

)- h. Q'uality Assurance Practices l 1. Other appropriate fields associated with the unique:

characteristics of the nuclear power plant.

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The NFSC shall be composed of.the following- -)

l Chairman (As' appointed - See Step 4).

l Man 6ger, Nuclear Licensing and Resource Management Division l Manager, Nuclear Production and Station Manager Manager, Nuclear Engineering Division l

Manager, Quality Assurance Division l l Safety and Security Director Consultants, as required, shall be appointed in writing by I the Senior Vice President, Nuclear Operations. i

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

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. Fort St. :Vrain #1 Technical-Specifications Amendment No., 36,56,69 Page'7.1-14 4 Chairman I

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The Chairman anc Alternate Chairman of.the NFSC shall be- J

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l appointed in writing by the Senior Vice President,.  !

Nuclear Operations and shall serve as members of the. I NFSC.

.I S. Consultants 1

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

6. Meetine Frecuency -

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.q The NFSC shall meet at least once per calendar quarter-during the initial year of facility operation following I

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fuel loading and at least once per six months I there&fter.

7. Ouorum I

A ouorum of the NFSC_shall consist of the Chairman or his designated alternate and a majority of' the NFSC members including alternates. No 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; )

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- Fort St. Vrain #1 Technical Specifications Amendment'No. 37,56,69 Page 7.1-18 personnel or an. outside fire protection firm:

(b) a biennial audit of the fire protection pregram and' implementing procedures; i (c) a triennial fire protection and l o s s ~.

preven +. ion inspection and audit utilizing an  !

outside qualified fire consultant.

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l (9) The Off site L'ose Calculation Manual and Process l Control Program and implementing procedures at i least once'per 24 months. .j l

(10) The Radiological Environmental Monitoring-  !

program and the res'Jits thereof at least once per 12 months. '

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(11) The performance of activities required by the Quality Assu'rance 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 p6r 12 months.

9. Authority k

l Tne NFSC shall report .to and advise the Senior Vice l President, Nuclear Operations on those areas of responsibility specified in 8.0, 8.b and 8.c above.

10. Reccrds l

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

I a. Minutes of each NFSC n:eeting shall be precared and l forwarded to the Senior Vice President, Nuclear i Operations within 30 days following each meeting,

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4 Fort St', Vrain )1 Technical ~ Specifications- .i Amendment No. 37,55,69,  ;

Page.7.1-19: ]

l. . b ', After' preliminary approval' by the Senior' Vice l President'4, Nuclear, Operations,.the. minutes.shall be.

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1 distributed to all NFSC members, and approved at the )

I 1 next.NFSC meeting. j

~l' c. Reports of~. reviews encompassed by Section 8.a, I above~ shall be forwarded to the Senior Vice Presioent, ' Nuclear Operations, .within 30 days l 1

L following-completion of the' review.

' i I d. Audit reports. encompassed by Section 8.c above l

I shall be forwa-ded to the' Senior Vice President, .)

Nuclear- Operations, 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 01 Technical Specifications

. Amendment No. 22,69

, Page 7.2-1 7.2 SAFETY _1!MITS, ADMINISTRATIVE CONTROLS Aoplica_t,ilip Applies to the administrative procedures to be followed in the event that a safety limit is exceeded.

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

Specification AC 7.2 - Action to be Taken if a Safety Limit is Exceeded, Administrate 1ve 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 immediately and reactor operations shall not be resumed until approval is received froc the NRC.

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

d. Thf Safety Limit Violation Report shall be submitted to the Com31ssion, the Chairman, NFSC and the Manager, Nuclear Production l and Station Manager within ten days of the violation.

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