ML20064C112: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
 
Line 14: Line 14:
| 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
| project =
| stage = Request
}}
}}



Latest revision as of 23:54, 31 May 2023

Application to Amend License NPF-12,modifying Containment Isolation Valve Table to Allow Entry Into Higher Mode W/Action Statement Re 821228 off-line Valve Trip Due to Personnel Error
ML20064C112
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 12/28/1982
From: Dixon O
SOUTH CAROLINA ELECTRIC & GAS CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML20064C114 List:
References
NUDOCS 8301040320
Download: ML20064C112 (3)


Text

-

SOUTH CAROLINA ELECTRIC & gas COMPANY POST OFFICE 764 COLuuslA. SOUTH CAROLINA 29218 O. W. DIXON, JR.

Nuc EAn OPERAT ONS December 28, 1982 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 Specification Change

Dear Mr. Denton:

On December 28, 1982, at approximately 9:25 a.m. the Virgil C. Summer Nuclear Station was tripped of f-line due to personnel error by an instrument technician performing routine plant testing. The plant is now ready to proceed to Mode 1, however, Technical Specification 3.6.4 does not allow transition ir.to higher modes of operation while in an action statement.

Specifically valves 9398A-SS and 9398B-SS, containment isolation valves in the sampling lines f rom steam generators A& B blowdown lines, failed the maximum isolation time requirements of Technical Specification 4.6.4.3. The plant then entered Action Statement C of Technical Specification 3.6.4. As stated above this action statement prohibits transition into higher modes of operation.

SCE&G requests that Technical Specification Table 3.6-1 be modified to allow entry into a higher mode of operation (see attached pages 3/4 6-20 and 3/4 6-20c). Although valve 9398C-SS remains operable, it has been included in this request as a precautionary measure.

SCE&G nas concluded that this does not involve an QQC)

M unreviewed safety question based on the following facts: g

1. the sample lines involved are small (3/8") high E) pressure secondary system lines that are exempt from (

10 CFR 50 Appendix J, Type C testing requirements.

2. these valves are currently in their containment isolation position (closed).

8301040320 821228 PDR ADCCK 05000395 P PDR

Mr. Harold R. Denton December 28, 1982 Page #2

3. these lines are equipped with manual isolation valves downstream which have also been closed.
4. continuous operation is allowed within the action I

statement indicating that the safety concern is that the valves are isolated in their safety position, not that they are immediately restored to operation.

5. alternate methods for sampling exist which provide representative samples and do not increase operator dose rates, namely via the Steam Generator Blowdown System through valves 550A-BD and 550D-BD or 10512-BD and 10513-BD for steam generator A and 550B-BD and 550E-BD or 10514-BD and 10515-BD for steam generator B and 550C-BD and 550F-BD or 10516-BD and 10517-BD for steam generator C.

It should be noted that because this is not a safety concern the additional shutdown of the primary plant to repair these valves is not justified. Additionally, this condition poses an economic concern for South Carolina Electric and Gas Company (SCE&G) and the South Carolina Public Service Authority (SCPSA). Because SCE&G's current generating configuration allowed several fossil units to be shut down, we are now required to purchase 300 MWe from neighboring utilities and operate a pumped storage facility to replace the Virgil C. Summer Nuclear Station's output. These sources of

energy are very limited. Restart of the Virgil C. Summer i Nuclear Station is the most feasible means of suppling our power needs.

This change has been approved by the Plant Safety Review Committee (PSRC) and the Nuclear Safety Review Committee (NSRC).

A check in the amount of twelve hundred dollars

($1200.00) required by 10 CFR 170 to process this change will be forwarded promptly.

l

i Mr. Harold R. Denton

! December 28, 1982

Page 43 -=

! We request your immediate attention to this matter.

Very truly yours, l

j $4 . / ,

l O. W. D xon, r.

l NEC:OWD/lkh i

h cc: V. C. Summe r G. H. Fischer

. H. N. Cyrus I

T. C. Nichols, Jr.

O. W. Dixon, Jr.

! M. B. Whitaker, Jr.

J. P. O'Reilly H. T. Babb D. A. Nau man C. L. Ligon (NSRC)

W. A. Williams , Jr.

R. B. Clary O. S. Bradham A. R. Koon M. N. Browne G. J. Braddick J. L. Skold s J. B. Knotts, Jr.

B. A. Bursey NPCF File

_ . . _ _ _ _ _ _ _ . _ _ .