ML20077F219
| ML20077F219 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 07/20/1983 |
| From: | Lee O PUBLIC SERVICE CO. OF COLORADO |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20077F222 | List: |
| References | |
| P-83242, NUDOCS 8308010299 | |
| Download: ML20077F219 (6) | |
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PUBLIC SERVICE COMPANY OF COLORADO P.
O. BOX 84O
- DENVER, COLORADO 802 Fort St. Vrain Unit No.1 Oscan u. tre P-83242 v,c
....oe,,1 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 DOCKET N0. 50-267
SUBJECT:
Fort St. Vrain Updated FSAR, Revision 1 Dear Sir.
Enclosed is one (1) signed original and twelve (12) additional copies of Revision 1 to the Updated Final Safety Analysis Report (Updated FSAR) for Fort St.
Vrain which has been prepared and is being submitted in accordance with 10CFR50, Section 50.71(3).
This revision includes the effects of changes made in the facility or procedures as described in the Updated FSAR; safety evaluations perfonned by PSC, either in support of license amendments or in support of conclusions that changes did not involve an unreviewed safety question; and analyses of new safety issues perfonned by or on behalf of PSC at Commission request.
Brief descriptions of the principal changes or additions to affected sections and appendices of the Updated FSAR, Revision 1, are included in Attachment A.
Other changes made in the FSAR, not requiring prior l
Commission approval pursuant to 10CFR50.59(a), and not yet reported to the Commission, are listed in Attachment B to this letter. These changes will be more fully described along with the results "of their safety evalua tions, as appropriate, in PSCo's regular report of 10CFR50.59 changes which will be submitted in early 1984.
Very truly yours,
- 0. R. Lee, Vice President Electric Production ORL/DCG:pa Attachments A - Description of Principal Changes Incorporated into Revision 1 of the Updated FSAR B - List of 10CFR50.59 changes not previously reported to the Commission 8308010299 830720 DR ADOCK 05000267 I
Attachment A P-83242 July 20,1983 APPENDIX A Add.d a brief discussion of the results of the nondestructive examination of the first fuel test element (FTE-1).
APPENDIX B Added new infonnation pertaining to the certification and use of ASTM A-36 steel.
Added information regarding independent verification of the. condition / position of critical equipment prior to return to service following clearance conditions as contained in previous PSC responses to NUREG-0737.
Incorporated those minor changes to or clarifications of the quality assurance program previ ously reported to the Commission in letter P-83203 (dated June 9, 1983).
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APPENDIX C Updated design criteria to reflect the steam generator penetration interspace pressure control modification.
APPENDIX D Added a brief evaluation of control room habitability and reactor building accessibility for post accident conditions as contained in previous PSC responses to NUREG-0737.
NOTE:
Where appropriate, sections were revised to use consistant terminology or make editorial clarification of descriptive material to achieve consistency with other sections in the FSAR. Minor typographical and editorial errors were al so ccrrected, i
Attachment A P-83242 July 20,1983 SECTION 7 Revi sions to this section added infomation concerning radiation monitoring of the steam generator penetration interspace, the addition of a sixty meter meteorological tower and associated instrumentation and a discussion of the first plateout probe renoval.
SECTION 9 Incorporated infonnation concerning control of heavy loads previously submitted to the Commission.
SECTION 10 Incorporated ISI program infomation pertaining to the secondary coolant system valves.
SECTION 11 Updated the discussion concerning operation of the radioactive liquid waste system per 10CFR20, including use of the reactor building sump as part of this systen (as requested by NRC Region IV in IE Inspection Report 83-06 dated llay 23, 1983).
Included infonaation concerning post accident sampling contained in previous PSC responses to NUREG-0737.
SECTION 12 Updated the infomation pertaining to the radiological emergency response plan and early warning system.
SECTION 13 Added new ma terial discus sing the ISI program in general and updated the summary of the related surveillance requirements.
SECTION 14 l
l Added updated infomation concerning masonry block walls and
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addressed the possibility of primary coolant leakage into the l
secondary coolant systen via the steam generator penetration interspaces.
Added a brief discussion of the validation of the Reactor Emergency Cooling Analysis (RECA-3) code.
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Attachm:nt A
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P-83242 July 20,1983 Description of Principal Changes Incorporated in Revision 1 to the Updated FSAR SECTION 1 Brief descriptions have been added to the design modification summary portion of this section to address the steam generator inters pace pressure control modi fication and meteorological equipment modifications.
SECTION 3 Infonnation was added to incorporate the comparison region method of reactor operation as approved by the Commission in Amendment 28 to the Facility Operating License.
A discussion of the first plateout probe removal and examination was inserted.
New material was added concerning the In-Se rvice Inspection and Testing (ISI) program pertaining to the reactor internals.
The results of the visual examination of the two fuel elements with graphite block web cracks were incorporated.
A discussion of the reserve shutdown system previously located in Section 4 was moved to Section 3 to improve continuity.
SECTION 4 A di scus sion of tne steam generator penetration interspace pressure control modification was added.
New information was added concerning the ISI program as related to the helium circulators and shutoff valves.
A modification to the helium circulator steam / water drains was incorporated and information pertaining to the reserve shutdown system was moved to Section 3.
SECTION 5 New sections were added concerning the ISI program pertaining to PCRV closures and penetrations.
SECTION 6 Several sections were updated to reflect the current ISI program and its applicabili ty to the steam / water dump system, PCRV penetration secondary closures and flow restriction devices, and the PCRV safety valves.
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter
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Public Service Company of Colorado
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Docket No. 50-267 i
Fort St. Vrain Unit No.1
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i AFFIDAVIT 1
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Lee, being duly sworn, hereby deposes and says that he is Vice President of Public Service Company of Colorado; that he is duly authorized to sign and file with the Nuclear Regulatory Commission Revision 1 of the Updated-FSAR; that he is familiar with the content thereof; and that the matters set forth therein are true and correct to the best of his knowledge, information and belief.
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R'. f.ee, Vice President i,
STATE OF deled
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COUNTY OF M
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Subscribed and sworn to before me, a Notary Public in and for on this M
day of
, 1983.
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l Notary Public y a 2 c. c. nzMM M, ca, fot33 My commission expires A,wr /f
, 1983.
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Attachment B P-83242 July 20,1983 FSAR CHANGES PER 10CFR50.59 (Not Previously Reported to the Commission)
As required by 10CFR50, Section 50.71(e-2(ii)), following is a list of the changes made under the provisions of 10CFR50, Section 50.59 which have not previously been submitted to the Canmission.
These changes will be more fully described, along with the results of their safety evaluations, as appropriate, in PSC's regular report of 10CFR50.59 changes which will be submitted in early 1984.
FSAR Section Description of Change 7.2 Control rod position information was removed from a multipoint recorder and is now processed by the data logger computer.
7.4 Hand switches were installed on the auxiliary control board to pennit manual control of the main steam bypass valves in the event of abandonment of the control roam.
11.1 A procedure was revised to pennit utilization of the Reactor Building Sump for dilution of radioactive liquid wastes in the event such dilution is necessary to meet the requirements of 10CFR20.
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