ML19337A406
| ML19337A406 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 08/15/1980 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Nichols T SOUTH CAROLINA ELECTRIC & GAS CO. |
| References | |
| NUDOCS 8009090789 | |
| Download: ML19337A406 (3) | |
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o-o UNITED STATES "g
NUCLEAR REGULATORY COMMISSION g
-E WASHINGTON, D. C. 20555
-o AUG 151990
- Docket No. S0-39S Mr. T. C. Nichols, Jr.
Vice President & Group Executive Nuclear Operations South Carolina Electric & Gas Company P. O. Box 764 Columbia, South Carolina 29281 Dear Mr. Nichols
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING TMI CONCERNS -
1 VIRGIL C. SUMMER NUCLEAR STATION, UNIT N0.1 We have reviewed your responses.to TMI-2 Action Plan Items II.B.3, II.F.1, and III.D.l.i.
The information we reviewed included that contained in Amendments 18 and 19 to the FSAR. We have concluded that additional information is required in order for.us to complete our review. Our requests for additional information are contained in the Enclosure to this letter.
We request that you provide this additional information not later than August 22, 1980.
If you cannot meet this schedule or if you require any clarification, please contact the staff's assigned project manager.
Sincere,ly L,
f4d
's Robert.Tedesco,As[istantDirector for Licensing Division of Licensing
Enclosure:
As stated cc w/ enclosure:
See next page THIS DOCUMENT CONTAINS 1_
P00R QUALITY PAGES 9009090 i
Mr. T.; C. Nichols, Jr.
AUG 1 5 Vice President,& Group Executive IM09 Nuclear Operations.
South Carolina Electric & Gas Company P. O. Box 764 Columbia, South Carolina 29281 cc: Mr. William A. Williams, Jr.
Vice President South Carolina Public Service Authority 223 North Live Oak Drive Moncks Corner, South Carolina 29461 Troy B. Conner, Jr., Esq.
Conner,-Moore & Corber 1747 Pennsylvania Avenue, N. W.
Washington, D. C.
20006 Mr. Mark B. Whitaker, Jr.
Group Manager - Nuclear Engineering & Licensing South Carolina Electric & Gas Company P. O. Box 764 Columbia, South Carolina 29218 Mr. Brett Allen Bursey Route 1, Box 93C
. Little Mountain, South Carolina 29076 Resident Inspector / Summer NPS c/o~ U. S. NRC P. O. Box 1047 Irmo, South Carolina 29063 i
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ETSB'C0FMEf4TS ON THE VIRGIL ~C.
SU's ER NUCLEAR STATION RESPONSE TO TMl CONCERNS
.(APRIL 1980)
'321.11 Additional Accident Monitoring Instrumentation (Effluent) 1 Action Plan II F.1~
In Amendment 18 of the FSAR'(Section 11.4) you propose to install a high range noble gas effluent monitor (RM-A13) in the main plant vent exhaust.
You are also required to install a high range noble gas effluent monitor.
for the reactor building purge exhaust since this path is an independent release line.
Clarify that the steam dump / safety and containment hydrogen purge exhausts will be monitored by high range noble gas effluent monitors.
If the installation of all of these monitors will be completed and calibrated by fuel loading, provide the information required in Item 2.1.8.b, Sections 1.8, and'2.B. given in the November 9, 1979 letter.
If, however, you can not complete: installation before fuel loading, then you should submit interim l
procedures and methods at this time, describing how you will quantify noble gas, particulate and radiciodine effluent releases (see Items 1.A.1.a.
1.A.I.b, 2.A.1 and 2.A.2 under Item 2.1.8.b in our letter dated fovember 9, 1979). Then you should complete the final installation of all the high range noble' gas effluent monitors and provide information required in Item 2.1.8.b,' Sections 1.B and 2.8, given in the November 9, 1979 letter, by January 1, 1981. Additional information is provided in NUREG-0694, "TMI-Related Requirements for New Operating Licenses," June 1980.
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321.12 Primary _ Coolant Sources'Outside~ Containment Action' Plan-II1.D.1.1
~a).
At' this ' time, before issuance of a full po.wr license, provide a description ofithe program you will implement to reduce leakage to as-low-as practical levels from systems nutside-cuntainment that could contain. highly radioactive-fluids during a. serious transient or' accident. Your description should contain adequate information
,egarding the method for the leak rate tests, their frequency, the test r
procedures for each system or subsystem and the. acceptance criteria for the tests.
Indicate the steps to be taken to minimize occupational radiation c.sposure, and assure system coatpleteness.
Specify the staffing and training requiremants, b)-
The program should racasure actual leakage rate: tit h the :;niams in operation and provide a sumary of the test results to NRC prior to issuance of a full power license.
c)
The program should use the design criteria for raiminizing leakages from systems 'outside cent ainment given in Soction 6.3.2.11.3, Amandnent 18 to the. I SAR, and preventive maintenance and quality-assurance programs.
'l For;fud her.information'for' Item 2, See NUREG-0694.
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' 3P.l.13 Post Accident Sampling i
Acti,on-P1an II.B.3-a);
You-have not: addressed. Action Plan II.B.3 in the Amendment 18 to Ihe FSAR. Before' issuance of a full-po;ter license prior to January 1, 1931, you should' complete the following requirements:
l (i) Submit a descriptive suc: nary of the interim provisions and procedures for sampling and analyzing the reactor coolanc and the-containment atmosphere. Your summary should include the interim nodifications ynu will need to conduct the phy-sical, che.nical and radiological analysis steps.
(ii) Provide a description and final system design of any new sampling
' station provisions and final modifications to the sa.:p'te handling l
and counting facilities to ' achieve analysis within the tite i.pc-cified -in Item 2.1.S.a, given in the flovember 9,1979 letter.
L b)
You should co.aplete the necessary improvements or installatien of new facilities not later than January 1, 1981.
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For further-information for Item 3, see !!UREG-0694.
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