ML20154J456

Amend 63 to License DPR-34,changing Tech Spec Section 7 Re Administrative Controls

ML20154J456
Person / Time
Site:	Fort Saint Vrain
Issue date:	09/15/1988
From:	Calvo J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20154J443	List: ML20154J440 ML20154J456 ML20154J462
References
NUDOCS 8809230030
Download: ML20154J456 (14)

Text

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~,, UNITED STATES

! e NUCLEAR REGULATORY COMMISSION

{ , W ASHING TON. D. C. 20666

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PUBLIC SERVICE COMPANY OF COLORADO

DOCKET NO. 50-767 FORT ST. VRAIN NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.63

!,1 cense No. DPR-34

1. The Nuclear Regulatory Comiss',on (the Comission) has found that:

4 A. The application for atendment by Public Service Company of Coloraco (the licenseel dated February 5, 1988 as suppler.ented June 23, 1988, complies with the standards and requirerents of the J Atomic Energy Act of 1954, as amended (the Act), and th Comission's  !

rules and regulations set forth in 10 CFR Chapter 1; 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 Corr.ission;

, C. There is reasonable assurance: (1)thattheactivitiesauthorized by this amendrtent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D. The issuance of this license amendrent will net be inimical to the

. corrnon defense and security or to the health and safety of the public; ard l

E. The issuance of this amendment is in accordance with 10 CFR Part 51 '

of the Comission's regulations and all applicable requirements have been satisfied.

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2. Accordingly, the license is arended by changes to the Technical  !

Specifications as indicated in the attachment to this license arendrent. [

andparagraph2.0.(2)ofFacilityOperhting1.icenseNo.OPR-34ishereby '

j amended to read as follows' i  !

(2) Technical Specifications The Technical Specitications contained in Appendices A and B, as [

revised through Amendment No,63, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specificationt.

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l 3. The license amende.ent is effecti,' n of its date of issuance.

l f0R THE NUCLEAR REGULATORY COMMIS$10N fe'd di-)w n

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' Jose A. Calvo. Directe I

! Project Directorate .'I i

! Division of Reactor Pro,ie a - 111 j j IV, V and Special Projects Office of Nuclear Reacter Regulation 1 i

Attachment:

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Changes to the Technical f Specificatters ,

l Date of Issuance: September 15, 1988

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. ATTACHMENT TO LICENSE AMENDMENT NO. 63 TO FACILITY OPERATING LICENSE NO. OPR-34 DOCKET NO. 50-267 Replace the following pages of the Appendix A Technical Specifications with the attached pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Insert 7.1-7 7.1-7 7.1-8 7.1-8 7.1-9 7.1-9 7.1-10 7.1-10 P 7.1-13 7.1-13 7.1-22 7.1-22 7.1-23 7.1-23 7.4-1 7.4-1 7.4-2 7.4-2 7.4-3 7.4-3 7.5-3 7.5-3 i

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. . Fort St. Vrain #1 Technical Specifications Amendment No. 36,56,63 Page 7.1-7 Authorized deviations co the working hour guidelines e shall be documented and available for Nuclear Regulatory Cc lission review.

3. Training

a. A retraining and replacement training prcgram for the facility staff shall be maintained under the j directior, of the Nuclear Training Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10CFR Part 55. Compliance with Section 5.5 of ANSI 18.1-1971 shall be achieved no later than six months following commemcement of- commercial operation.

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

c. The Technical Advisors shall have a bachelor degree or equivalent in a scientific or engineering discipline with specific training in plant design l

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Fort St. Vrain #1

.'" Technical Specificati Amendment No. M . E6.ggs Page 7.1- 8 and response and analysis of the plant for transients and accidents. An initial training and retraining program for the Technical Advisors shall l be maintained under the direction of the Nuclear l Training Manager. The Technical Advisors shall also receive training in plant design and layout, including the capabilities of instrumentation and controls in the Control Room.

Specification AC 7.1.2 - Plant Operations Review Cemmittee (p0RC), Admini grative Contro_1s The organization, responsibilities, and authority of the '

PORC shall be as follows:

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

Chairman: Station Manager Technical / Administrative Services Manager Support Services Manager (Radiation Protection Manager)

Superintendent of Operations Superintendent of Maintenance Superintendent of Nuclear Betterment Engineering I

' Fort St. Vrain #1 Technical Specifications Amendment No. 36, 56, 63 Page 7.1- 9 Results Engineering Supervisor  ;

l Administrative Shift Supervisor I

Superintendent of Technice.1 Services Engineering i Nuclear Training Manage-

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 l shall participate as voting members in PORC activities at any one time.

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

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

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! 5. Responsibilities l The PORC shall be responsible for:

.' '. Fort St. Vrain #1

',- Technical Specifications Amendment No. 42,63 Page 7.1-10

a. Re.iew of all procedures required by Technical l Specification 7.4(a), (b), (c) and (d) and changes thereto, and any other proposed procedure or changes to approved procedures as determined by the Station Manager to affect nuclear safety,

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

c. Review of all proposed changes to the Technical Specifications.

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d. Review of all proposed changes or modifications to -

plant systems or equipment that affect nuclea-safety.

e. Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering the evaluation and

. recommendations' to prevent rectrrence to the Manager, Nuclear Production and to the Chairman of the Nuclear Facility Safety Committee.

f. Review of all Reportable Events.

g. Review of facility operations to detect potential '

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nuclear safety hazards.

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Fort St. Vrain #1 Technical Specifica?> ions Amendment No. 36, E6, 63 Page 7.1-13 e) I,.strumentation 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:

I Chairman (As appointed - See Step 4)

Manager, Nuclear Licensing and Fuels Division Manager, Nuclear Production Division Manager, Nuclear Engineering Division Manager, Quality Assurance Division Safety and Security Director l Consultants, as required, shall be appointed in writing by 1 the Vice President, Nucitar Operations.

3. Alternates l

Alternate members, if required, shall be appointed in writing by the Vice President, Nuclear Operations; however, no more than two l

l alternate members shall participate as voting members in NFSC activities at any one time.

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o FORT ST. VRAIN NUCLEAR GENERATING STATION ADMINISTRATIVE AND DEPARTMENTAL MANAGEMENT ORGANIZATION CHART -

Chairman and Chief Executive Officer l

Vice President Nuclear NFSC Operations NFSC - Nuclear Facility Safety Committee PORC - Plant Operations Review Committee

• Serves as the Radiation Protection Manager Manager Manager Manager Manager Quality Nuclear Licensing Nuclear Nuclear Assurance and Engineering Production Division Fuels Division Division Division l

Nuclear Training b 8' . " Technical / 2'S"#3' Administrative W*rA 1

Manager S

Manager ..

M n ga Services Manager yg

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o PORC 5h w2 FIGURE 7.1 - 1

FORT ST. VRAIN NUCLEAR GENERATMfG STATION CONDUCT OF OPERATIONS CHART .

Manager Nuclear .

Production Dnnsson i

i j Support Staten Technica!/

Services Manager Adrranctrative Manager *

• Services j l SLO

• Manager PORC 4

i Supenneendent Superintendent Supenntendent Superintendent Eclear Maintenance Operations Techtwcal Betterrnent Sennces E Engineering lSto. ,

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Health]- Results Administrative p Phr.ics Engineering Shitt 3, m an g c+

Supennsor Supervisor Severvisor y3-m ISLO L

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i 4""g Leher the Stasion Manager or the Supenneendent of Operations (as 2 m 7 shallpossessa Sermor License .31 Serves as the Radisson Protecten W Equipment i $ o^ :s Reactor Auniliary Technical 3 -

PORC Plant Operations Review Cornnuste Opesators Operators Tenders Advisors wQ m ,,

SLO - Seno tecensedOpnator LO - ticensed Opesata h l m*

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Figure 7.1-2

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• Fort St. Vrain #1

- Technical Specifications Amendment No. 37. 63 Page 7.4- 1 7.4 PROCECURES - ADMINISTRATIVE CONTROLS Applicability Applies to administrative procedures which will govern plant operations.

Objective To ensure that written procedures will be maintained to define requirements for plant operation.

Specification AC 7.4 - procedures. Administrative Controls

a. Written procedures shall be established, impiemented and maintained covering the activities i referenced below:

1. The applicable procedures recommended in l Appendix A of Safety Guide 33, November, 1972.

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2. Refueling operations.

3. Surveillance and test activities of safety- 1 related eouipment.

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4. Security Plan implementation. <

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'5. Emergency Plan ir plemente. tion.

l l 6. Process Cuntrol Program (PCP) implementation.

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Fort St. Vrain #1

.. Technical Specifications Amendment No. 37, 56, 63 Page 7.4- 2

7. Offsite Dose Calculation Manual (ODCM) implementation.

8. Quelity Assurance Program for effluent and environmer.t t i monitoring using the guidance in Regulatory Guide 1.21, Revision 1. June,1974 and Regulatory Guide 4.1, Revision 1, April *,

1975. ,

b. Procedures and administrative policies of a) above, and changes thereto, shall be reviewed by the PORC, l or a subcommittee thereof, and approved by the 1

l appropriate management prior to implementation.

l Procedures shall be reviewed periodically as set forth in Administrative Procedures.

Security Plan procedures, and changes thereto, shall be reviewed by the Plant Operations Review l Committee, or a subcommittee thereof, and approved by the designated Plant Security Offluer prior to implementation.

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

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

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Fort St. Vrain #1 Technical Specifica Amendment No. 37, *} ions Page 7.4-3

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

3. The change is documented, reviewed by the l PORC, or a :ubcommittee thereof, and approved l by the appropriate management within 14 days of implementation.

d. Procedures for personnel radiation protection shall be prepared consistent with the requiraments of 10 CFR Part 20, and shall be approved, hiaintained,

. and adhered to for all operations involving personnel radiation exposure.

Respiratory protective equipment shall be provided in accordance with 10 CFR 20.103. _ _

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Fort St. Vrain #1 Technical Specifications Amendment No. 37,63 Page 7.5-3 ced surveillance, in-service inspection, routine maintensnce, special eaintenance (describe maintenance),wasteprocessing,and refueling. Tho dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totaling less -

than 20% of the individual total dose need nut be accounted for. In the aggregate, at least 80% of the whole body dose received from external sources shall be assigned to specific

, major work functions,

c. Monthly Operating Report A reutine coerating report covering the operation of the unit during the previous month shall be submitted prior to the f'af teenth calendar day of the following month.

l Submittal shall be to the U. S. Nuclear l Regulatory Commission, ATTN: Document Control l l Desk, Washington, D. C. 20555, with a copy to the appropriate NRC Regional Administrator, t

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