ML20203L146
| ML20203L146 | |
| Person / Time | |
|---|---|
| Site: | Summer |
| Issue date: | 08/18/1986 |
| From: | Nauman D SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 8608250033 | |
| Download: ML20203L146 (4) | |
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e Cgo um, bgg 29218 Nuclear Operations SCE&G A SCJlNR limary August 18, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuciaar Regulatory Commission Washington, DC 20555
SUBJECT:
Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. HPF-12 Regulatory Guide 1.97 Request for Additional Information
Dear Mr. Denton:
In a letter from your staff dated June 18, 1986, South Carolina Electric and Gas Company (SCE&G) received a request for additional information on conformance to Regulatory Guide 1.97. This letter is hereby being forwarded as a partial response to that request for information. Due to the high degree of required interaction with various groups both internal and external to SCE&G, additional time is needed to provide all of the requested information. Therefore, SCE&G will provide the remaining information no later than October 31, 1986.
If you should have any questions, please advise.
tp y durs, Lh D./. N man AM: DAN /dwf Attachment pc:
- 0. W. Dixon, Jr./T. C. Nichols, Jr.
C. L. Ligon (NSRC)
E. H. Crews, Jr.
R. M. Campbell, Jr.
E. C. Roberts K. E. Modland O. S. Bradham R. A. Stough D. R. Moore G. O. Percival J. G. Connelly, Jr.
R. L. Prevatte W. A. Williams, Jr.
J. B. Knotts, Jr.
Group Managers NPCF i
W. R. Baehr File i
C. A. Price 8608230033 860318 DR ADOCK 0500 5
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ATTACHMENT A R gulf tcry Guida 1.97 Rrquest f r Additicn:1 Inform tian The following items meet the requirements of Regulatory Guide 1.97.
QUESTION:
1.
Range requirement deviation -- the licensee should provide the range monitored for the four variables listed and justify any deviation from the regulatory guide.
RESPONSE
a)
Wide Range Steam Generator Level -- The span covers from tube sheet to 24 inches above primary moisture seperator, b)
Narrow Range Steam Generator Level -- 20 feet (top of tubes to bottom of secondary separators).
c)
Pressurizer Level -- Span covers top to bottom of_right cylindrical portion.
It does not include end caps.
d)
Refueling Water Storage Tank Level -- Span covers bottom to top of tank.
QUESTION:
2.
Control rod position -- the licensee should provide the information required by Section 6.2 of Supplement No. I to NUREG-0737 for this variable, identify any deviations and justify those deviations identified.
RESPONSE
Control Rod Position -- Virgil C. Summer Station utilizes the Westinghouse Digital Rod Position Indication System.
Range -- Full-in to Full-out for each control rod.
Seismic -- No.
- of Channels -- One Indication Panel.
=
Control Room Indication Device -- Visual graphical indication.
Power Supply -- Non IE Environmental Qualification -- None.
E0F/TSC Indication -- Yes.-- All in, Not in.
QUESTION:
4.
Containment pressure -- the licensee should expand the existing range for this variable or justify the use of the existing range.
RESPONSE
Containment Pressure -- The span covered at Virgil C.
Summer Station for post accident monitoring is -5 to 175 PSIG. Narrow range monitors from -5 PSIG to 15 PSIG. Wide range monitors from -5 PSIG to 175 PSIG.
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ATTACHMENT A R:gul:t:ry Guida 1.97 R: quest fer Additian:lInformati:n QUESTION:
7.
Accumulator tank level and pressure -- the licensee should provide the information required by Section 6.2 of j
Supplement No. I to NUREG-0737 for this variable, identify any deviations and justify those deviations identified.
j
RESPONSE
Accumulator Tank Pressure -- LT921, 923, 925, 927, 929, 931 Range -- 0-800 PSIG Qualification -- Mechanical only, mild environment Seismic -- Yes
- of Channels -- 6; 2 per tank Control room Indication Device -- Analog Indicator Power Supply -- Non IE EOF /TSC Indication -- Yes Accumulator tank level will be addressed in a future submittal.
6 QUESTION:
- 16. Steam generator pressure -- the licensee should provide the range monitored by this instrumentation and the highest and lowest safety valve settings
RESPONSE
Steamline Pressure -- IPT 474, 484, 494 (typical)
Lowest safety valve setting -- 1176 PSIG Highest safety valve setting -- 1235 PSIG Range -- 0-1300 PSIG QUESTION:
- 27. Wind direction -- the licensee should provide the instrument range information required by Section 6.2 of Supplement No. 1 to NUREG-0737 for this variable, identify any deviations and justify those deviations identified.
RESPONSE
Wind Direction -- IST 8503, 8505 Range -- 0-540*
Accuracy --
1.136*
Starting Speed -.75 mph Damping Ratio -- 40 Delay Distance -- 3.3 feet Page 2 of 3
ATTACHMENT A g
Regulatery Guids 1.97 Requ stfar AdditicnalInfcrmatien QUESTION:
- 28. Wind speed -- the licensee should provide the instrument range information required by Section 6.2 of Supplement No.
I to NUREG-0737 for this variable, identify any deviations and justify those deviations identified.
RESPONSE
Wind Speed -- ISI 8503 Range -- 0-110 mph Accuracy --
.208 mph Starting Threshold -
.6 mph Distance Constant -- 5 feet QUESTION:
- 29. Estimation of atmospheric stability -- the licensee should provide the instrument range information required by Section 6.2 of Supplement No. I to NUREG-0737 for this variable, identify any deviations and justify those deviations identified.
RESPONSE
Estimation of Atmospheric Stability Range -- -10*F to +15'F Accuracy of System -.0230*F / 15 min.
.0380*F / 5 min.
QUESTION:
30.
Primary coolant and sump sampling capability -- the licensee should provide the instrument range information required by Section 6.2 of Supplement No.,1 to NUREG-0737 for this variable, identify any deviations and justify those deviations identified.
RESPONSE
Primary Coolant and Sump Sampling Capability -- Grab Sample Gross Activity -- 1pC1/ml to 10 Ci/ml Gamma Spectrum -- Isotopic Analysis Baron Content -- 0-6000 ppm Dissolved Hydrogen -- 5-2000 cc/kg pH -- 1-13 NOTE:
Sump Sampling is conducted through the Residual Heat Removal System which draws suction from the Reactor Building Sump during post LOCA events.
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