ML20005G996
| ML20005G996 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 01/11/1990 |
| From: | Weiss S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20005G992 | List: |
| References | |
| NUDOCS 9001240020 | |
| Download: ML20005G996 (8) | |
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UNITED STATES -
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'8 NUCLEAR RECULATORY COMMISSION
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I PUBLIC SERVICE' COMPANY OF COLORADO
' DOCKET NO. 50-267 FORT ST.- VRAIN NUCLEAR.CENERATING STATION
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AMENDMENT TO FACILITY OPERATING LICENSE-j Amendment No. 76 License No. DPR-34
-1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Public Service Company of Colorado (thelicensee)datedSeptember 14, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended'(the Act),andtheCommission'sregulationssetforthin10CFRChapterI; B.
' The facility will operate in conformity with the application. as amended, the provisions of the Act, and the regulations of the Comission; i.
C.
.There is reasonable assurance:
(1) that the activities authorized
'by this amendment 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; o,
D.
The issuance of this license amendment will not be inimical to the i!
comon defense and security or to the health and safety of the public; i:
and 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 l
been satisfied.
i 9001240020 90o131 fDR ADOCK 05000267 jt.
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Accordingly, the license is-amended by changes to the Technical
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Specifications as indicated in the attachment to this license arrendment,-
and paragraphs 2.D.(2) and 2.D.(5).of Facility Operating License No. DPR-34 are hereby amended to read as follows:
(2).TechnicalSpecifications ThetTechnical. Specifications contained in Appendices A and.B, as revised through Amendment No. 76, are hereby incorporated in' the l
s license. The licensee shall operate the facility in accordance with the-Technical Specifications.
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.(5) Fire Protection-The licensee shall implement'and maintain in effect all provisions c
of the approved fire protection program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated May 18, 1989 subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Comission only if those changes would not adversely affect the ability to achieve and i
maintain safe shutdown in the event of a fire.
3.
The license. amendment is effective as of its-date of-issuance.
o FOR THE NUCLEAR REGULATORY COMMISSION QA L-d Seymour H. Weiss, Director Non-Power Reactor, Decommissioning and Environmental Project Directorate Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 11, 1990 o
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' ATTACWENT TO' LICENSE AMENDMENT NO. 76 TO FACILITY OPERATING LICENSE NO. DPR-34
. DOCKET NO. 50-267 1
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I Replace the following pages of the Appendix A Technical Specifications with
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the attached pages. The revised pages are identified by amendment number and F
contain vertical:11nes indicating the areas of change.
Remove Insert 1'
4.10-1 4.10-1 4.10-2 4.10-2(a) 4.10 -
4.10-4 4.10-5 4.10-6 4.10-7 4.10-8 4.10-9 5.10-1 5.10-1 e
5.10-2 5.10-3 5.10-4 5.10-5 5.10-6 7.1-4 7.1-4 7.1-11 7.1-11 7.4-2 7.4-2 l
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.j Technical-Specifications j, '
Amendment No. 76' Page 4.10 '
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.4.10' FIRE SUPPRESSION SYSTEMS - LIMITING CONDITIONS FOR OPERATION.
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- (These. requirements have.been deleted.
Refer to the Fire
'l Protection Program Plan for Fire Protection' Operability I
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. Requirements'.)-
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Forg 5%.'Urain al-Technical Specifications-f" Amendment No', 76 Page.5,10-1
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c 5.10 FIRE SUPPRESSION SYSTEMS - SURVEILLANCE REQUIREMENTS l:
(These requirements have been deleted.
Refer to the Fire 1,
Protection Program Plan for - Fire Protection Operability l.
~ Requirements.)
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Fort St. Vrain 01 Technical Specificationsi sO-f
,4 Amendment No. 76 W
Page 7.1-4
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(4).During-theJ performance o f.
reactor startup,
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reactor l shutdown. 'and recovery - from reactor
- trip, two-licensed operators must be in the Control room.
(5)'All core alterations shall be' observed and d
directly supervised by either a licensed Senior T-Reactor' Operator or Senior Reactor Operator Limited; to Fuel-Handling who has no other i
concurrent responsibilities during this operation.
(6) An operator or technician qualified in radiation i
. protection procedures shall be present at the facility at.all times that there is fuel on site.
- l (7) Fire Brigade staffing _ requirements have been
.ll incorporated into the Fire Protection Program
~ l Plan.
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TechnicaliSpecifications-
. Amendment No. 76 y
Page.7.1-11 e.- Investigation of all violations of the Technical Specifications.
including- -the-preparation and-
. forwarding. of. reports covering the' evaluation'and recommendations to prevent:-
recurrence' to' the i
s Manager, Nuclear Production and Station Manager and
'to the Chairman-'of the Nuclear. Facility Safety Committee, l
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Review-of all Reportable Events, g.
Review of facility operations-to detect potential
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nuclear ~ safety. hazards, j
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Performance :of'special reviews, investigations, and reports thereon as-requested by the Chairman of the Nuclear Facility Safety Committee.
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Review of-the Plant Security Plan and implementing procedures.
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Review of the plant Radiological Emergency Response Plan and impl'ementing procedures.
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Review of the Fire Protection Program Plan and l-implementing procedures.
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-Fort St..Vrain #1 f # ""._
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Technical Specifications-Amendment No..76 Page 7.4 '
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.7.
Offsite Dose? LCalculation Manual (ODCM)_
4 implementation.
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Quality Assurance Program.for effluent and
. environmental monitoring using the guidance in w
q Regulatory GuideL1.21, Revision 1, June,1974' and Regulatory Guide 4.1, Revision 1,
- April, g-1975.
-l 9.
Fire Protection Program Plan implementation, b.
Procedures and administrative policies of a) above, and changes.thereto, shall be reviewed by the PORC, or - a subcommittee thereof, and approved by the
. appropriate management prior to implementation.
Procedures shall be reviewed periodically as set forth in Administrative Procedures.
.s Security Plan procedures, and changes thereto, t
shall be reviewed by the' Plant Operations Review i
Committee, or a subcommittee thereof, and approved by the designated Plant Security Officer. prior to implementation.
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Temporary changes to procedures of a) above may be l
made provided-1.
The intent of the original procedure is not altered.
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