ML20002E474
| ML20002E474 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 01/23/1981 |
| From: | Nichols T SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8101280119 | |
| Download: ML20002E474 (3) | |
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x SOUTH CAROLINA ELECTRIC a gas COMPANY bf;,
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CotuMe:A, South CAnouNA 29218 b:
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Janaury 23, 1981 v.a p...,., -. c.- c.ume ea. on z
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Mr. Harold R. Denton, Director Office of Nuclear Reactor a w '" tion U. S. Nuclear Regulatory Commission Washington, D C. 20555
Subject:
Virgil C. Summer Nuclear Station Docket No. 50/395 Response to Comments Received j
at Janaury 7, 1981 Meeting in l
Bethesda l I li
Dear Mr. Denton:
l The following is in response to the NRC Summary of Site Visit held on November 12-14, 1980, at Surmer Nuclear Station as discussed in our meeting in Bethesda on January 7, 1981.
A.
Auxiliary Feedwater System (1) Manual closure capability to effect valve closure with the accumulator air source will be provided in the control room. However, due to avail-ability of control board space, the switches may not be in optimum l'
positions from a human factors standpoint.
(2) The accumulator air systems will be modified to permit periodic test-ing of their operability. Technical Specifications will include this ll testing in surveillance requirements consistent with Section 4.6.4.2 of Techniu 2 Specliteations.
(3) We will either modify the alarms addressed in Position 6 to indicate l
that high flow isol.atien has been initiated or provide this indica-tion on new switches (1.aition 1).
The setpoint for the alarms will be changed to the valve isolation'setpoint if they are not modified as centioned above.
(4)
Independent reset capability will be provided for automatic AFW initia-tion (valveo full open) and automatic high flow isolation (valve full closed). As stated in one above, the switches required for this func~
tion may not be in optimun positions from a human factors standpoint.
(5) This reset capability will be added to the control room evaluation pancis.
(6)
See answer to number 3.
(7) The controls for the TDFP steam supply valve will be modified to provide
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Mr. Harold R. Denten January 23',1981 Page Two capability from the control room to isolate flow to a faulted steam generator assuming a single failure. An accumulator air source will be added similar to that on the flow control valve.
The schedule for implementation of this change depends on availability of components.
Estimate one year.
(8) We will provide a description of the design basis of the AFW system as requested in Position 8.
Scheduled for February 1.
B.
Steam Generator Atmospheric Relief Valves We will modify the interlocks for the S. G. PORVs as requested in Position 9.
The schedule for implementation of this change depends on availability of components.
Estimate one year.
C.
Potential Design Deficiencies in Bypass, Override and Reset Circuits of Engineered Safety Features In our letter to you dated January 9, 1981, we committed to review and test all Engineered Safety Features (ESF) control circuits with respect to deficiencies in bypass, override and reset of ESF action.
The bypass features on the control room ventilation isolation circuits mentioned in the audit repo t are to te deleted due to changes in the HVAC System.
D.
Discrepancy Between FSAR and the As-Built Schematic FSAR Figure 7.2-1 will be updated to reflect current design in the next amendment.
E.
(1) Trip Setpoints and Margins I
As stated previously, a response to this item is scheduled for July 1, 1981.
(2) Field Audit for Separation of Electrical Equipment and Systems The independent field audit report was submitted by letter dated January 6, 1981. We will provide additional comments on the discre-pancies by January 23, 1981.'
f (3)
Failure Modes and Effects Analysis (FMEA) Interface Requirements A response to this item was submitted by letter dated December 16, 1980.
(4)
IE Bulletin 79-27, Loss of Non-C' ass IE Instrumentation and Control Power System Bus Dur._g Operatica We consider this item to be closed based on the October 31, 1980-response.
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D
Mr. IIarold R. Denton January 23, 1981 Page Three (5) Remote Shutdown Panel Modifications The final design documentation has been submitted.
The power supriies that do not have an independent source in the remote shutdown panel are those that are not needed immediately upon evacuation of the control room.
This is discussed in the Fire Hazards Analysis.
The additional set of drawings that were requested should be delivered the week of January 19, 1981.
l (6) Post Accident Monitoring Instruments A response to NUREG-0737 is being provided in Amendment 23 to the FSAR.
l F.
ISE Concerns on Separation Requirements for Class IE Redundant Inst _rumentation Cables Internal to the Process Instruments and Control Cabinets A copy of the response to ISE item 395/80-2-02 has been forwarded.
acference our letter to Mr. O'Reilly, dated January 16, 1981.
Very truly yours, fA G
a T. C. Nichols, Jr.
SMC: JAW: CAI':TCN: glb cc:
V. C. Summer G. 11. Fischer T. C. Nichols, Jr.
E. H. Crews, Jr.
I
- 0. W. Dixon, Jr.
D. A. Nauman O. S. Bradham l
W. A. Williams, Jr.
A. A. Smith A. R. Koon R. B. Clary J. B. Knotts, Jr.
J. L. Skolds B. A. Bursay NPCP/Whitaker File l
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