ML20247G734
| ML20247G734 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 09/14/1989 |
| From: | PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML20247G726 | List: |
| References | |
| NUDOCS 8909190132 | |
| Download: ML20247G734 (11) | |
Text
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ATTACHMENT 1
SUMMARY
OF PROPOSED CHANGES 8909190132 890914 PDR ADOCK 05000267 P
FDC E_____-.___-.
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SUMMARY
OF PROPOSED CHANGES Facility Addition of License Condition 5), page 5 of 5.
Operating License (Enclosure 1)
LCO 4.10 Deletion of the specifications in this section.
SR 5.10 Deletion of the specifications in this section.
AC 7.1.1 Deletion of the Site Fire Brigade membership requirements, page 7.1-4.
AC 7.1.2 Addition of the Fire Protection Program Plan to PORC Responsibilities, page 7.1-11.
AC 7.4 Addition of the Fire Protection Program Plan implementation, page 7.4-2.
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ATTACHMENT 2 PROPOSED CHANGES L _._
Fort St. Vrain f
Technical Specifications j
License Information.
Enclosure (1) to AEC Letter dated 12/21/73 l
Amendment No.
Page 5 of 5 (4) Early Shutdown The licensee is not authorized to operate the reactor 1
L (above 2 percent of full power) for electric power production af ter June 30, 1990.
l (5) Fire Protection l
The licensee shall implement and maintain in effect all l
provisions of the approved fire protection program as l
described -in the Final Safety Analysis Report for the i
facility and as approved in the SER dated May 18, 1989 l
subject to the following provision:
l The licensee may make changes to the approved fire l
protection program without prior approval of the l
Commission only if those changes would not adversely l
affect the ability to achieve and maintain safe I
shutdown in the event of a fire.
E.
This license is subject.to all Federal, State, and local standards imposed pursuant to the requirements of the Federal Water Pollution Control Act of 1972.
3.
This license is effective as of the date of issuance and shall expire at midnight, September 17, 2008.
FOR THE ATOMIC ENERGY COMMISSION "0RIGINAL SIGNED BY:"
A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing Attachments:
Appendices A and B - Technical Specifications Date of Issuance: December 21, 1973
Fort St. Vrain 01 Technical Specifications Amendment No.
Page 4.10-1 4.10 FIRE SUPPRESSION SYSTEMS - LIMITING CONDITIONS FOR OPERATION I
(These requirements have been deleted.
Refer to the Fire l
Protection Program Plan for Fire Protection Operability l
Requirements.)
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- 1. e Fort St. Vrain #1 Technical Specifications Amendment No.
l Page 5.10-1 l
1-5.10 FIRE SUPPRESSION SYSTEMS - SURVEILLANCE REQUIREMENTS l
(These requirements have been deleted.
Refer to the Fire-l Protection Program Plan for Fire Protection Operability 1
-l Requirements.)
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I Fort St. Vrain 01 Technical Specifications Amendment No.
Page 7.1-4 (4) During-the performance of reactor startup, reactor shutdown, and recove ry from reactor
- trip, two licensed operators must be in the control room.
(5) All core alterations shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.
(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) Fire Brigade staffing requirements have been l
incorporated into the Fi re Protection Program l
Plan.
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Fort St. Vrain #1
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Technical Specifications Amendment No.
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 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 of special reviews, investigations, and reports thereon as requested by the Chairman of the Nu: lear Facility Safety Committee.
i.
Review of the Plant Security Plan and implementing procedures.
j.
Review of the plant Radiological Emergency Response Plan and implementing procedures.
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Review of the Fire Protection Program Plan and l
l implementing procedures.
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Fort St Vrain #1 Technical Specifications Amendment No.
Page 7.4-2 l
7.
Offsite Dose Calculation Manual (ODCM) implementation.
8.
Quality Assurance Program for effluent and j
environmental monitoring using the guidance in Regulatory Guide 1.21, Revision 1, June,1974 I
and Regulatory Guide 4.1, Revision 1,
- April, 1975.
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Fire Protection Program Plan implementation.
1 b.
Procedures and administrative policies of a) above, I
and changes thereto, shall be reviewed by the PORC, i
or a subcommittee thereof, and approved by the l
appropriate management prior to implementation.
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Procedures shall be reviewed periodically as set l
l forth in Administrative Procedures.
I Security Plan procedures, and changes thereto, shall be reviewed by the Plant Operations Review l
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Committee, or a subcommittee thereof, and approved l
o by the designated Plant Security Officer prior to implementation.
c.
Temporary changes to procedures of a) above may be made provided:
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The intent of the original procedure is not
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altered.
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1 ATTACHMENT 3 NO SIGNIFICANT HAZARDS CONSIDERATION ANALYSIS 1
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l NO SIGNIFICANT HAZARDS CONSIDERATION ANALYSIS l~
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EVALUATION The guidance provided in Generic Letters 86-10 and 88-12 allows licensees to remove Technical Specifications (TS) covering Fire Protection / Suppression Systems and to amend the License by adding a'new standard License condition.
An equivalent level of Fire Protection will be maintained at Fort St.
Vrain by implementing the Fi re Protection Operability Requirements which are contained in the Fire Protection Program Plan.
Additionally, as directed in Generic Letter 88-12, the Administrative Controls Section of the TS has been augmented to support the Fire Protection Program Plan (FPPP) and the Fire Brigade staffing requirements have been removed from the TS and incorporated into the FPPP.
The Fort St. Vrain Fire Protection Program Plan, including the operability requirements as identified in Section 6.1 of the
- Plan, provides adequate detection and suppression capability in accordance with Appendix A to BTP APCSB 9.5-1, in accordance with Appendix R to 10CFR50.
II.
CONCLUSION Based on the above evaluation, it is concluded that operation of Fort St. Vrain in accordance with the proposed changes will not (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety.
Therefore, this change will not increase the risk to the health and safety of the public nor does it involve any significant hazards consideration.
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