ML20006B792

Proposed Tech Specs Re Administrative Title Changes to Section 7.1

ML20006B792
Person / Time
Site:	Fort Saint Vrain
Issue date:	01/25/1990
From:	PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20006B780	List: ML20006B779 ML20006B784 ML20006B792
References
NUDOCS 9002050359
Download: ML20006B792 (16)

Text

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ATTACHMENT 2 1  ;

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=i-PROPOSED CHANGES t

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' 9002050359 900125 i

{DR= ADOCK 05000267 PDC ,.

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

Amendment No.

Page,7.1-L j 7.1 ORGANIZATION, REVIEW, AND AUDIT-ADMINISTRATIVE CONTROLS

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Applicability Applies to the lines of authority and responsibility for the -

operational safety of the facility, and the organization for periodic review and audit of-facility operation.

Objectives '

To define the principal , lines of authority andl responsibility for providingfcontinuing review, evaluation,:

and improvement of the plant operational. safety.-

SPECIFICATION AC 7.1.1' - ORGANIZATION, ~ ADMINISTRATIVE CONTROLS.

1. RESPONSIBILITY

a. The Manager, Nuclear Production and Station Manager shall be resoonsible for overall unit operation - and shall delegate in writing the~ succession to this; responsibility during his absence.-

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b. The Shift Supervisor (or during his absence'from'the control room and Shift- Supervisor's. office',- a-designated individual) shall'be_ responsible for the-control' room command- function. A management. 0 l directive to this effect, signed by the.1Vice President, Nuclear Operations shall 1>e reissued -to all station personnel on an annual basis.

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.. Fort St. Vrain #1 Technical Specificatiens  :

Amendment Ne. -

- Page 7.1-3 l (3)The Vice President, Nuclear Operations shall  !

have corporate responsibility for overall plant "

nuclear safety and sh'all take any measures needed to ensure acceptable performance of t.he l staff in operating, maintaining, and providing  ;

technical support to the plant to ensure nuclear ,

safety.

I (4) The individuals who train the operating staff. l and those who carry out health physics and ,

-quality assurance functions may report to the appropriate onsite manager; however, they 'shall- e i

have sufficient organizational freedom to ensure  !

their independence from operating pressures. *

b. Unit Staff i

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

Table 7.1-1,

f (2) A licensed operator must be in.the-control room .t

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at all times when fuel is in the reactor, (3) During shutdown and refueling conditions, an- .;

individual (other than the Technical Advisor) -l with a. valid R0 _(or SRO)' license' shall.be 1

l present in the control room. During. a11 Hother i l conditions, an- individual -(other :'than: the Technical Advisor) with a valid SRO license  !

O shall.be present in.the control room..

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" Fort-St. Vrain #1-

.? Technical Specificatiens ,

4 Amendment No.  ;

. Page 7.1-8c

5. TRAINING ];

a. A retraining and replacement training program for the facility staff shall be maintained under the direction l of .the Nuclear Training and Support Manager, and shall  ;

meet or exceed the requirements and recommendations of-Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 i CFR 55.

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b. A training program for the Fire' Brigade shall be maintained under the direction of.the Nuclear Training  :

.i and Support . Manager, and shall, meet or -exceed the

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l 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. The Tet..'enical Advisors shall have a bachelor's degree or l equivalent in a scientific. or engineering discipline with specific training in plant design and response and analysis of the plant for transients and' accidents. An' initial training and retraining . program for- the l Technical Advisors shall be maintained under the l l direction of the Nuclear Training and Support Manager.

1 h The Technical Advisors shall also receive training in l-plant design and layout, including the capabilities'of instrumentation and controls in the control room.

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FortSt.Vrainil Technical Specifications l Amendment No, *

, Page 7.1-9 l

_ Specification AC 7.1.2 - Plant Operations Review Committee (PORC), Administrative Controls , i The organization, responsibilities, and authority of the i

PORC shall be as follows:  ;

1. Membership r

The Plant Operations Review Committee shall be composed  :

of the following:  !

Chairman: Manager, Nuclear Production and Station  :

Manager  !

l Nuclear Training and Support Manager ,

Superintendent of Chemistry and Radiation Protection i (Radiation Protection Manager)  ;

Superintendent of Operations i Maintenance Department Manager -

Systems Engineering Manager  ;

Superintendent of I&C Maintenance -

Operations Manager l

2. Alternates r

An alternate chairman _ a nd 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 as voting members in PORC activities at any one time, i

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q Fort St. Vrain #1 Tcchnical Specifications Amendment No.

. Page 7.1-13

e. Instrumentation and Control

f. Radiological Safety

g. Mechanical and Electrical Engineering

h. Quality Assurance Practices

1. Other -. appropriate fields associated with the unique characteristics of the nuclear power plant.

2. Membership - .

The NFSC shall be composed of the following:

Chairman (As appointed - See Step 4)

Manager, Nuclear Licensing and Resource Management Division .

Manager, Nuclear Production and Station Manager.

Manager, Nitelear Engineering Division -

tianager, Quality Assurance Division '

l Nuclear Training and Support Manager .;

Safety and Security Director Consultants, as -required, shall be appointed in writing by_ .

l the Vice President, Nuclear 0perations.

3. Alternates Alternate members, if required, shall .be appointed in writing by -

l' the Vice President', Nuclear _ Operations;-however, no more than two '!

alternate members shall. participate' as voting. members in NFSC i acttvities at any one time. -l i

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Fort St. Vrain #1 Technical Sp;cificaticns' Amendment No.

- Page 7.1-14  !

i 4.

Chairman The Chairman and Alternate Chairman of the NFSC shall be  ;

l appointed in writing by the Vice President, Nuclear 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. Meetino 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. 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:

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

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F;rt St. Vrain #1 Technical Specificaticns-Amendment No.

. Page_7.1-18 personnel or an outside fire protection firm; i

(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 Dose Calculation Manual and Process  ;

Control Program and implementing procedures at least once per 24 months, t (10) The Radiological Environmental Monitoring ,

Program and the results thereof at least once  ;

per 12 months. E' (11)The performance of activities required by the-Quality Assurance Program to meet the- i 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. Authorig 1

l Yhe NFSC shall report to and advise the Vice President -

Nuclear Operations on those. areas of responsibility l specified in B.a. 8.b and 8.c above. [,

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10. Records  ;

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

a. Minutes of each NFSC nieeting shall be prepared and

, j forwarded to the Vice President, Nuclea'r Operations  ;

within 30 days following each meeting.

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" Fort St.'Vrain #1-Technical Specificati;ns j Amendment No.  !

. Page 7.1-19 l

l b. After preliminary approval by the Vice President, -

Nuclear Operations, the minutes shall be distributed to all NFSC members, and approved at'the next NFSC i

meeting.

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

completion of the review.

d. Audit reports encompassed by Section 8.c, above l shall be forwarde'd to the 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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" Fcrt-St. Vrain #1 Technical Specifications; Amendment No..

- Page 7.5-4 Each monthly operating report shall include:

1. A narrative summary of operating experience during the ' report period relating to safe- operation of the facility,-including major safety-related maintenance.

2. Report of any single release of.

radioactivity or radiation exposure which accounts for~ more than 10% of the allowable annual values.

3. Indications of failed fuel.resulting from 1; radiated fuel examinations, completed during the report period.

4. The monthlyf statistical information contained in Regulatory Guide 1.16.

d. Annual Radiological Envi ronmental ' Monitorino Report A report on -_the Radiological Environmental' Monitoring Program for the previous calendar l year. shall be subinitted to. the Nuclear l Regulatory Commission in; accordance with'-

l 10 CFR 50.4 as.a separate document by_May l'of-each year.

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" Fort St. Vrain #1 .

Technical SpecificatiCns Amendment No.

Page 7.5-5  :

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The Annual -Radiological Environmental  ;

Monitoring Reports shall. include summaries, interpretations, and an analysis of trends of l the results of the radiological environmental! '!

i monitoring activities for the report period. .

including a comparison 'with _ pre-operational' studies, operational controls (as appropriate), and previous . environmental j monitoring- reports, and an assessment'of the  !

i observed impacts of the plant operation on the  !

environment. The reports shall also include the results of land-use censuses required by. ,

t Specification ELCO 8.2.1. 1 The Annual Radiological Environmental l Monitoring Reports shall include the -results '

of analysis of.all radiological environmental '

samples and of all measurements taken during  !

the period pursuant to the Table and Figures I in the ODCM, as .well as summarized' and tabulated results of these analyses and measurements.in the format of the tableiin the  !

Radiological Assessment Branch-- Technical- ,

1 Position, Revision 1, November,,1979.- In the i 3

event that some individual -results are not i 1,

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.t ATTACHMENT 3 TO P-90001 NO SIGNIFICANT HAZARDS CONSIDERATION ~

ANALYSIS e

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NO SIGNIFICANT HAZARDS CONSIDERATION ANALYSIS I. EVALUATION OF CHANGES Changes are made to Administrative Controls Specifications AC 7.1.1, AC 7.1.2, and. portions of AC 7.1.3 to incorporate changes to certain Fort St. Vrain management titles. These changes do not result in any decrease in management control over nuclear operations; nor do they decrease the effectiveness and competency of the Plant Operations Review Committee or Nuclear Facility Safety Committee. The addition of the Nuclear Training and Support Manager to the NFSC Membership . enhances NFSC review capabilities. The address change for the Annual Radiological Environmental Monitoring Report is in accordance with 10CFR50.4.

II. CONCLUSION Based on the above evaluation, it is concluded that operation of Fort St. Vrain in accordance with the proposed changes will 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, or involve a significant reduction in a margin of safety. Therefore, this change will not increase any risk to the health and safety of the public nor does it involv'e any significant hazards.

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4 4 ATTACHMENT 4-TO P-90001' SAFETY ASSESSMENT-l

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r SAFETY ASSESSMENT ,

1.0 INTRODUCTION AND BACKGROUND

This letter. requests an- amendment to the Administrative -

Controls Section (Section 7) of the Fort St. Vrain Technical Specifications.- This amendment will reflect management changes at Fort St. Vrain, adds the Nuclear Training .and Support  :

Manager to the NFSC Membership, and corrects an address.for the i Annual . Radiological Environmental Monitoring Report. This-amendment will update the. Technical Specifications to ' reflect -

current organizational titles and further meet federal regulations. '

b 2.0 EVALUATION A. Specifications AC 7.1.1 and AC 7.1.3  !

The title of Senior Vice President, Nuclear Operations has beca 3 changed to Vice President, Nuclear Operations. This results l from a change in management which the NRC was-previously -

notified about in PSC Letter (P-89373), dated September- 22, '

1989. This change does not result in a ' decrease of any required organizational competencies. t B. Specifications AC 7.1.1.5~and AC 7.1.2.1  !

The duties of the Nuclear Support Manager have been combined-with the duties of the Nuclear Training Manager. These specifications have been changed to- reflect these combined responsibilities. This change does not decrease management control over. nuclear operations, nor decrease the effectiveness' and competence of the Plant Operations Review Committee.-

C. Specification AC 7.1.3.2 [

i The Nuclear Training and Support Manager has- been added to the

• NFSC Membership. This enhances NFSC .overall review  !

capabilities.

q L D. Specification 7.5.1.d s

The address for the Annual Radiological Environmental:

Monitoring Report has been revised to be in accordance with the address requirements of 10CFR50.4.

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3.0 ENVIRONMENTAL CONSIDERATION

l This amendment proposal relates to changes-in administrative procedures or requirements. This amendment proposal . involves no significant increase in the amounts, and no significant  !

change in the types of any ' effluents -that may be released-offsite, and- there will be no significant increase in individual or cumulative occupational radiation exposures. j i

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4.0 CONCLUSION

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Based on the considerations' discussed abeve, (l')'there is  ;

reasonable assurance that the health and safety of the. public  !

will not be endangered by. operation in the proposed manner, and- '

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(2) such activities will be conducted in compliance with the- 1 Commission's -regulations, and the issuance of the amendment I will not be inimical to the common defense and security.or' the health and safety of the public. -]

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