Letter Sequence Request |
|---|
|
Results
Other: 05000267/LER-1983-043-01, /01T-0:on 831011,during Spec LCO 4.1.9 Review, Assumptions Supporting Analysis Discovered Nonconservative, Obviating Basis for Spec.Interim Conservative Guidelines Followed Until Analysis Completed, ML20082A843, ML20082S949, ML20083F063, ML20084J011, ML20091E302, ML20095A385, ML20125D934, ML20202E952, ML20212G878, ML20214W452, ML20216H730, ML20236U722, ML20237E005
|
MONTHYEAR05000267/LER-1983-043-01, /01T-0:on 831011,during Spec LCO 4.1.9 Review, Assumptions Supporting Analysis Discovered Nonconservative, Obviating Basis for Spec.Interim Conservative Guidelines Followed Until Analysis Completed1983-10-25025 October 1983
/01T-0:on 831011,during Spec LCO 4.1.9 Review, Assumptions Supporting Analysis Discovered Nonconservative, Obviating Basis for Spec.Interim Conservative Guidelines Followed Until Analysis Completed
Project stage: Other
ML20082A8431983-11-0707 November 1983
RO 83-43:on 831011,util Notified NRC of Various Nonconservative Errors Made in Original Analyses Which Constitute Basis of Tech Spec 4.1.9.GA Technologies Provided Interim Curves Which Corrected Deficiencies
Project stage: Other
ML20082S9491983-11-30030 November 1983
Forwards Figure for Limiting Condition for Operation 4.1.9-1 Re Circulation Flow/Core Power,To Replace Figure Submitted w/831107 Ltr.Portions of Less Conservative Figure Deleted. Limit Will Be Observed Until Tech Spec Changed
Project stage: Other
ML20083F0631983-12-15015 December 1983
Proposed Tech Specs Revising Limiting Condition for Operation 4.1.9 Re Core Region Temp Rise
Project stage: Other
ML20083F0611983-12-15015 December 1983
Application for Amend to License DPR-34,revising Tech Spec Limiting Condition for Operation 4.1.9 Re Core Region Temp Rise,Per Previous Commitments.Class III Amend Fee Encl
Project stage: Request
ML20086R7281984-02-24024 February 1984
Responds to Request for Addl Info Re Proposed Amend to Limiting Condition for Operation 4.1.9 Re Average Core Temp During Shutdown
Project stage: Request
ML20084J0111984-04-0606 April 1984
ORNL Assistance in Evaluating Licensing Request - Fsv Limiting Condition for Operation 4.1.9, Monthly Rept for Mar 1984
Project stage: Other
ML20091E3021984-05-0909 May 1984
Interim Rept on ORNL Assistance in Evaluating Licensing Request - Amend of Fort St Vrain Reactor Tech Spec Limiting Condition for Operation 4.1.9
Project stage: Other
ML20095A3851984-08-14014 August 1984
Forwards Response to ORNL Concerns & Proposal Identified in NRC .Basis for Discussion of Ornl/Util Concerns & Resolution of Issues Delaying Implementation of Revised Limiting Condition for Operation 4.1.9 Discussed
Project stage: Other
ML20098H1721984-08-21021 August 1984
Provides Replies & Comments to Util Re Tech Spec Limiting Condition for Operation 4.1.9 in Advance of 840823 Meeting W/Util in Arlington,Tx
Project stage: Meeting
ML20099H7931984-11-20020 November 1984
Submits Addl Info Requested by NRC During 840823 Meeting Re Proposed Amend to Limiting Condition for Operation 4.1.9 Concerning Automated Orifice Valve Adjustments.Work Continuing on Listed Remaining Issues
Project stage: Meeting
ML20125D9341985-05-20020 May 1985
Submits Current Status of Work on Tech Spec Limiting Condition for Operation 4.1.9 Re Core Region Temp Rise. Calculational Differences Between Thermal/Hydraulic Analyses Being Investigated.Summary of Open Items Provided
Project stage: Other
ML20133K6751985-10-17017 October 1985
Notifies That Draft Proposed Rev to Tech Spec Limiting Condition for Operation 4.1.9 Re Core Region Temp Rise Will Be Submitted for Review by 851122
Project stage: Draft Other
ML20137E4941985-11-22022 November 1985
Forwards Draft Rev to Tech Spec Limiting Condition for Operation 4.1.9 Re Min Helium Flow/Core Region Temp Rise for Review.Formal Request for Amend to License DPR-34 Will Be Submitted Upon Resolution of NRC Comments
Project stage: Draft Request
ML20141B7451986-03-28028 March 1986
Summary of 860313 Meeting W/Util in Arlington,Tx Re Tech Spec Limiting Condition for Operation 4.1.9 Covering Frequency of Manipulation of Reactor Controls.Supporting Documentation Encl
Project stage: Meeting
ML20211E9171986-06-13013 June 1986
Advises That Formal Application for Tech Spec Rev Re Limiting Condition for Operation 4.1.9, Min Helium Flow & Max Core Region Temp Rise, Will Be Submitted by 860703. Extension Required for Resolution of NRC 860606 Comments
Project stage: Request
ML20202E9261986-07-0909 July 1986
Forwards Application for Amend to License DPR-34,changing Tech Specs to Incorporate Min Helium Flow & Max Core Region Temp Rise Surveillance Requirements.Fee Paid
Project stage: Request
ML20202E9371986-07-0909 July 1986
Application for Amend to License DPR-34,changing Tech Specs to Incorporate Helium Flow & Max Core Region Temp Rise Surveillance Requirements
Project stage: Request
ML20202E9521986-07-0909 July 1986
Proposed Tech Specs,Incorporating Min Helium Flow & Max Core Region Temp Rise Surveillance Requirements
Project stage: Other
ML20214W4521986-10-16016 October 1986
Review of Proposed Tech Spec Change:Core Inlet Orifice Valves/Min Helium Flow & Max Core Region Temp Rise, Technical Evaluation Rept
Project stage: Other
ML20237E0051986-10-16016 October 1986
Forwards Final Version of Facility Limiting Condition for Operation 4.1.9 Technical Evaluation Rept for Review & Approval.Related Info Encl
Project stage: Other
ML20214W4361986-12-0505 December 1986
Forwards Review of Proposed Tech Spec Change:Core Inlet Orifice Valves/Min Helium Flow & Max Core Region Temp Rise. Requests Submittal Addressing Staff Concerns within 45 Days of Ltr Date
Project stage: Approval
ML20212G8781987-01-14014 January 1987
Advises That Util Will Submit Revised Proposal for Tech Spec 4.1.9 Re Min Helium Flow & Max Core Region Temp Rise by 870225.Util Finalizing Curves That Determine Allowed Outage Times for DHR Equipment for Inclusion in Tech Specs
Project stage: Other
ML20216J4731987-06-25025 June 1987
Forwards Application for Amend to License DPR-34,changing Tech Spec Limiting Condition for Operation 4.1.9 to Reduce Potential for Flow Stagnation & Prevent Excessive Fuel Temps in Core & Spec 5.1.8 to Incorporate Requirements.Fee Paid
Project stage: Request
ML20216H7301987-06-25025 June 1987
Proposed Tech Specs,Adding Definition of Calculated Bulk Core Temp & Core Average Inlet Temp for Determination of Core Temp
Project stage: Other
ML20216H7221987-06-25025 June 1987
Application for Amend to License DPR-34,changing Tech Spec Limiting Condition for Operation 4.1.9 to Reduce Potential for Flow Stagnation & Prevent Excessive Fuel Temps in Core & Spec 5.1.8 to Incorporate Associated Requirements
Project stage: Request
ML20236U7221987-08-0606 August 1987
Addendum to Review of Proposed Tech Spec Change:Core Inlet Valves/Min Helium Flow & Max Core Region Temp Rise, Limiting Conditon for Operation 4.1.9, Technical Evaluation Rept
Project stage: Other
ML20236U5041987-11-23023 November 1987
Forwards Amend 57 to License DPR-34 & Safety Evaluation. Amend Revises Tech Specs to Ensure Sufficient Helium Coolant Flow to Prevent Overheating of Fuel While in Low Power or Shutdown Modes
Project stage: Approval
1985-10-17
[Table View] |
Text
e hPuulic Service-geg-lrt.i.
2420 W. 26th Avenue, Suite 1000, Denver, Colorado 80211 July 9, 1986 Fort St. Vrain Unit No. 1 P-86451 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 ATTN: Mr. H. N. Berkow, Director Standardization and Special Projects Directorate Docket No. 50-267
SUBJECT:
PROPOSED TECHNICAL SPECIFICATION CHANGE, CORE INLET ORIFICE VALVES /
MINIMUM HELIUM FLOW and MAXIMUM CORE REGION TEMPERATURE RISE
REFERENCES:
(1) PSC letter, O. R. Lee to J. T. Collins, dated 12/15/83 (P-83403)
(2) PSC letter, H. L. Brey to E. J. Butcher, dated 11/22/85 (P-85442)
(3) PSC letter, H. L. Brey to H. N. Berkow, dated 4/30/86 (P-86333)
(4) PSC letter, D. W. Warembourg to J. T. Collins dated 10/25/83 (P-83346)
Dear Mr. Berkow:
This letter is a submittal of proposed changes to Fort St. Vrain Technical Specification LC0 4.1.9, Minimum Helium Flow and Maximum Core Region Temperature
- Rise, and a proposed new Technical Specification, SR 5.1.8, to incorporate the associated surveillance requirements.
Public Service Company of Colorado (PSC) requests NRC f-Q0 '
ir=8ausaggg ye aA i,,
P-86451 July 9, 1986 approval of these Technical Specifications and issuance of a license amendment.
This submittal supersedes PSC's previous proposed change for LC0 4.1.9 (Reference 1).
The considerations discussed in previous draft submittals (References 2 and 3) have been included, and NRC comments identified in a telephone conversation on June 6,
- 1985, have been addressed. provides a Summary of Proposed Changes to the existing license. Attachment 2 includes the Proposed Changes to the existing license.
The format for additions to the existing license reflects the format being incorporated into the Technical Specification Upgrade Program. contains the Significant Hazards Consideration for the proposed change, in accordance with 10CFR50.92.
This change does not involve a significant hazard.
In accordance with NRC guidance provided during the June 6, 1985 telephone conversation, PSC will continue to operate during the current outage with the existing LCO 4.1.9, as supplemented by the Figure 4.1.9-1 and 4.1.9-2 curves that were committed to on an interim basis in Reference 4.
In the event that an amendment has not been issued prior to the next startup, PSC intends to use the attached proposed Technical Specification for startup and subsequent operation.
In accordance with the provisions of 10CFR170, an application fee of
$150.00 is enclosed If you have any questions or comments concerning the enclosed information, please call Mr. M. H. Holmes at (303) 480-6960.
Very truly yours, R. O. Williams, Jr.
Vice President Nuclear Operations R0W/JPL/ paw Attachments cc: Albert J. Hazle Colorado Department of Health j
s FORM (B) 371-70-4033 23.i/io2e auly 9, 1986 Pusuc SERVICE COMPANY OF COLORADO DATE FORT SAINT VRAIN THE FIRST INTERSTATE BANK OF DENVER, N.A.
V 07047 e=au ^r DENVER. COLORADO PAY "** One Hundred Fif ty Dollars and no/100 ----------------- DOLLARS
$--150.00--
VOIO AFTER SO DAYS PUBLIC SERVICE COMPANY OF COLORADO OlVISION ACCOUNT h<(g&w ff m
rc r
+
U. S. Nuclear Regulatory Commission
"S' THE Cagr Washington, D. C. 20555 ER L-
_J n'OOOOOO 70 4 7n' s; LO 20000 abs:
5 4 3 9 5 7 Lii' REMITTANCE ADVICE. PLEASE DETACH FOR YOUR RECORDS.
THE ABOVE CHECK IS IN PAYMENT FOR THE FOLLOWING ITEMS.
V 07047 YOUR l
ACCOUNT TO BE CH ARGED DESCRIPTION AMOUNT INVOICE t
Perform Control l Res Chgi orcer Coce 8ScacesOntv>
4812!67 54 Technical Specification Fees per 150.00 I
attached letter P-86451 I
I i
1 i
l i
i i
L i
l i
l 1
I l
l L
PUBLIC SERVICE COMPANY OF COLORADO
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION
.i, In the Matter
)
)
Public Service Company of Colorado
)
Docket No. 50-267
]
Fort St. Vrain Unit No. 1
)
AFFIDAVIT i
R.
O.
- Williams, Jr., being first duly sworn, deposes and says:
That he is Vice President, Nuclear Operations, of Public Service Company of Colorado, the Licensee herein, that he has read the I
foregoing Application of Amendment to Appendix A of Facility i
Operating License and knows the contents thereof, and that the
.l statements and matters set forth therein are true and correct to the j
best of his knowledge, information and belief.
1
.m R. O. Williams, Jr.
Vice President Nuclear Operations STATE OF
[Made
)
)
COUNTY OF glasu
)
Subscribe and sworn to before me, a Notary Public on this
/4 If day of 44 1986.
/
/
W Motary Public ye2 4 C. /OMM.
h, u J'o O 3 My commission expires
//a ad/~ / 7
, 198.
7 f
i
_...,
