ML20235R395
| ML20235R395 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 10/31/1987 |
| From: | Stachew J EG&G IDAHO, INC. |
| To: | Heitner K Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20235R365 | List: |
| References | |
| CON-FIN-D-6023 NUDOCS 8710080033 | |
| Download: ML20235R395 (1) | |
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T P 09/30/87 TSF Doc 2009H Disk 01731 Job'38256 Proof 3 _
JLL NOTEGRAM 1
October,198)P T0:
Dr. Kenneth Heitner Phillips. Building, MS P-700 Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 FROM J. C. Stachew, EG&G Idaho, Inc.
TRANSMITTAL OF DRAFT TER FOR PLANT PROTECTIVE SYSTEM TRIP SETPOINTS FOR FORT ST. VRAIN NUCLEAR GENERATING STATION (06023).
reactor Regulation, Ref: (a) INEL Assistance To The Office of Nuclear
" Review of Plant-Sps.cific Licensing Actions for Operating Reactor Issues" (FIN D6023) l i
(b)
- 0. R. Lee 1tr to E. H. Johnson, Proposed Changes to Sections 2.1, j
3.3, 4.0, 5.0, LCO 4.4.1, and SR 5.4.1 of The Fort St. Vrain Technical Specifications, P-85214, June 21, 1985, Public Service Company of Colorado.
(c)
H. N. Berkow ltr to R. F. Walker, Fort St. Vrain - Plant Protection System Trip Setpoints, January 24, 1986, U. S. Nuclear j
Regulatory Commission.
(e)
R. F. Walker ltr to H. N. Berkow, Technical Specification Change Request'To The Plant Protective System Trip Setpoints, May 15,1986, Public Service Company of Colorado.
l l
Enclosed is the draft Technical Evaluation Report (TER) for the Plant Protective System (PPS) Trip Setpoints for the Fort St. Vrain Nuclear 8710000033 871001 DR ADOCK 05000267 p
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P 09/30/87 TSF Doc 2009H Disk 0173I Job 38256 Proof 3 JLL Generating Station. Public Service Company of Colorado (PSC) in Reference (b) submitted plant protective system trip setpoints for the Fort St. Vrain Technical Specifications that accounted for instrumentation uncertainties as well as other upgrade considerations.
In Reference (c), the NRC submitted a draf t SER and reauested PSC to resubmit only the trip setpoint uncertainty material from their earlier letter.
Reference (d) evaluated the NRC draft SER against the PSC resubmittal, (Reference c) assuming that questions related to which setpoint changes required additional safety analyses to be done and the corre,ctness of such added safety analyses had already been addressed as part of the NRC draft SER preparation. PSC responded to the seventeen issues raised in Reference (d) and resubmitted the Technical Specification changes-for only those PPS functions that are currently in the existing Fort St. Vrain Technical Specifications.
This work is being conducted for Mr. P. Shemanski of the Office of Nuclear Reactor Regulation, Division of Licensing - PWR-B under the Reference (a) 189 for the Fort St. Vrain Nuclear Generating Station.
JCS:bs Enclosure As Stated cc:
E. C. Anderson K. L. Heitner, NRC-DL L. Magleby C. Obenchain I
b
P 09/30/87. TSF ' Doe:2009H Disk 0173I
' Job 38256 Proof 3 _ _
.JLL p
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DEFT ENCLOSURE EG&G TECHNICAL EVALUATION REPORT
' PLANT PROTECTIVE SYSTEM TRIP SETPOINTS FOR FORT ST. VRAIN NUCLEAR GENERATING STATION-S l
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