ML20079H953: Difference between revisions

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| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS
| document type = OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING, TEXT-LICENSE APPLICATIONS & PERMITS
| page count = 3
| page count = 3
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| stage = Request
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Latest revision as of 00:40, 27 September 2022

Application to Amend License NPF-12,revising Tech Specs Re Combustible Gas Control,Per Generic Ltr 83-37.Tech Specs for Reactor Vessel Head Vent Valves Meet NUREG-0737,Item II.B.1 Requirements
ML20079H953
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 01/18/1984
From: Dixon O
SOUTH CAROLINA ELECTRIC & GAS CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML20079H954 List:
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.1, TASK-TM GL-83-37, NUDOCS 8401240138
Download: ML20079H953 (3)


Text

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p SOUTH CAROLINA ELECTRIC & GAS COMPANY Post oppica 7s4 COLUMetA. SOUTH CAROLINA 29218 O. W. DixON, JR.

vien pR..io NT January 18, 1984 NuCLEAn OPERAT:ONb Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Virgil C. Summer Nuclear Station Docket. No. 50/395 '

Operating License No. NPF-12 NRC Generic Letter 83-37

Dear Mr. Denton:

On November 1, 1983, the NRC issued Generic Letter No. 83-37, "NUREG-0737 Technical Specifications." The NRC Staff requested that South Carolina Electric and Gas Company (SCE&G) review its Technical Specifications, identify deviations or absence of a technical specification and submit an application for a license amendment in the event any deviations were identified. SCE&G has reviewed its Technical Specifications concerning NUREG-0737 items scheduled for implementation after December 31, 1981, and provides the following comments.

The model technical specification for Reactor Coolant System (RCS) vents addresses Pressurizer Power Operated Relief Valves (PORVs) and Reactor Vessel Head Vent Valves (RVHVVs) in one (1) technical specification. The Virgil C. Summer Nuclear Station Technical Specifications currently contain a separate technical specification for PORVs and RVHVVs. The existing technical specification for the RVHVVs meets the requirements of clarification (11) on NUREG 0737, Item II B.1 in that inservice testing of ASME valves in accordance with Section XI is specified. The RVHVVs are included in the Inservice Inspection Program and are tested in accordance with ASME Section XI as specified. Therefore, no additional RCS vent specifications are considered necessary.

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LMr. Harold R. Denton NRC Generic Letter 83-37 January'18, 1984

-Page #2 The model technical. specification for Chlorine. Detection-Systems is not- applicable to the Virgil C. Summer Nuclear Station. As discussed in the Final Safety Analysis Report, chlorine is handled in accordance with recommendations of Item C.2'of Regulatory Guide 1.95. Chlorine is stored in single containers'having an inventory of'150 pounds or less.

. Additionally,.it is stored. adjacent to the-water treatment building which is greater than 150 meters from the control room air intake. No changes have been made in the' storage of chlorine onsite and-it is SCE&G's position that technical specifications on chlorine detection are unnecessary.

The Virgil'C. Summer Nuclear Station Technical Specifications currently contain a technical specification for Combustible Gas Control. A deviation exists in our facility's technical.

specification and the model technical specification provided in Enclosure 3 of the Generic Letter. Our facility's technical specification for Combustible Gas Control does not have an action statement. pertaining to-the inoperability of two (2) hydrogen analyzers as found in the model technical specification. [SCE&G requests an amendment to the Virgil C.

Summer Nuclear Station Technical Specifications revising the Combustible Gas Control specification as provided on Attachment 1.)

SCE&G has determined that al finding of'no-significant hazards consideration is appropriate in that the proposed change is within the scope of approved Staff guidance as delineated in Generic Letter 83-37.

This amendment has been reviewed and approved by our Plant Safety Review Committee (PSRC) and the Nuclear Safety Review Committee (NSRC). A check in the amount of Four Thousand Dollars ($4000.00)- is enclosed for processing this change.

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Mr.. Harold R. Denton NRC Generic Letter 83-37 January 18, 1984 Page 63 If there are any questions, please contact us at your convenience.

Very truly yours, O. W. xon, J WRM:OWD/fjc cc: V. C. Summer T. C. Nichols, Jr./O. W. Dixon, Jr.

E. H. Crews, Jr.

E. C. Roberts W. A. Williams, Jr.

D. A..Nauman J. P. O'Reilly Group Managers O. S. Bradham C. A. Price C. L. Ligon (NSRC)

.G. J. Braddick D..J. Richards NRC Resident Inspector J. B. Knotts, Jr.

NPCF File

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