ML20077D153

Application to Amend License NPF-12,changing Tech Specs to Reflect Installation & Calibr of Condensate Demineralizer Backwash Effluent Monitor RM-L11 Prior to Startup After First Refueling Outage

ML20077D153
Person / Time
Site:	Summer
Issue date:	07/22/1983
From:	Dixon O SOUTH CAROLINA ELECTRIC & GAS CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20077D154	List: ML20077D153 ML20077D160
References
NUDOCS 8307260394
Download: ML20077D153 (2)

Text

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.9 SOUTH CAROLINA ELECTRIC & GAS COMPANY -

Post orrics 7s4 COLUMBIA. SOUTH CAROLINA 29218 O. W. DixoN, JR.

pm..**"'

vic July 22, 1983 NucteAn OpenarioNS 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 Technical Specifications - RM-Lll License Condition 2.C(21)

Dear.Mr. Denton:

License Condition 2.C(21) of the Virgil C. Summer Nuclear Station Operating License-requires the South Carolina Electric and Gas Company-(SCE&G) to install and calibrate the condensate demineral-izer backwash. effluent monitor RM-Lll prior to startup after the first refueling outage. This letter serves to inform you of the completion of this action and requests appropriate revisions to  :

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the Technical . Specifications to reflect- the use of monitor RM-Lll.

Changes (a) - (d) on the attached marked up Technical Specifica-tion pages incorporate RM-Lil into the Technical Specifications and define appropriate surveillance requirements. The proposed i Action Statement 36 is modeled after Action Statement 33 but recognizes that-this'is a batch sample and that it must meet sampling requirements for the resin as well as the liquid portion. Because of the expected low activity of this pathway, no requirement for redundant calculation or line valving is necessary. The change denoted'as (d) defines the appropriate Analog Channel Operational Test for a batch monitor. This secondary side system has an alarm on its local control panel but not in the control room. A finding of no significant hazard is justified because the addition of this monitor' represents an increase 'in our radiological monitoring capability.

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Mr. Harold R.~Denton July 22, 1983 Page #2 c

l Additionally,~an error in.the Technical Specifications has v been corrected on. Table 3.3-12, 1.b, Nuclear (Processed Steam Generator) Blowdown Effluent Line RM-L7 or FM-L9 [see change (e) ] . Monitors RM-L7 and RM-L9 control a batch release, not a continuous release as implied by Action Statement 32.

Therefore, action:is changed from 32 to 31 as appropriate.

Because this change does not impact either-accident analyses

'or margins of safety, a finding of no significant hazard is

. jus tified.

These changes have been reviewed and approved by the Plant Safety Review Committee and the Nuclear Safety. Review Committee. A check in the amount of Four Thousand Dollars

($4000.00) is enclosed for processing of this change.

If you require additional information, please contact-us.

Very trul yours, O. W. D'xon, . ,

'/fjc cc: V..C. Summer T. C. Nichols, Jr./O. W. Dixon, Jr.

E. H.. Crews, Jr.

E. C. Roberts

. H. N. Cyrus J. P. O'Reilly I Group / General Managers O. S. Bradham R. B. Clary C. A. Price l A. R. Koon.

C. L. Ligon (NSRC)

G. J.'Braddick

- J. C. Miller i J. L..Skolds J. B. Knotts, Jr.

H. G.-Shealy NPCF File (Lic./Eng.)

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