ML20077C321
| ML20077C321 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/22/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20077C320 | List: |
| References | |
| NUDOCS 9412010144 | |
| Download: ML20077C321 (4) | |
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[f",'%y 25 UNITED STATES j
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 2056M001 i
SAFETY EVALVATION BY THE OFFICE OF NUCLEAR REACTOR REGULATI0tl RELATED TO AMENDMENT NO.101 TO FACILITY OPERATING LICENSE NO. DPR-77 i
AND AMENDMENT NO.183 TO FACILITY OPERATING LICENSE NO. DPR-79 l
TENNESSEE VALLEY AUTHORITY SE0V0YAH NUCLEAR PLANT. UNITS 1 AND 2 i
DOCKET NOS. 50-327 AND 50-328 1.0 INTRODUCIL0ff By application dated September 9,1994, the Tennessee Valley Authority (the,
licensee) proposed an amendment to the Technical Specifications (TS) for Sequoyah Nuclear Plant (SQN) Units 1 and 2.
The requested changes would add the main steam valve vaults to the exclusion areas specified in the footnote to Specification 4.6.1.1.
2.0 EVALVATION Surveillance Requirement (SR) 4.6.1.1.a specifies the requirements for verification of the containment penetrations that are necessary to ensure containment integrity.
It requires that containment integrity be demonstrated at least once every 31 days by verifying that all penetrations not capable of being closed by operable containment automatic isolation valves and that are required to be closed during accident conditions, are closed by' valves, blind flanges, or deactivated automatic valves secured in their isolation positions.
A footnote to this SR lists exceptions to the surveillance interval.
It specifies that valves, blind flanges, and deactivated automatic valves that are located inside the annulus or containment that are locked, sealed or otherwise secured in the closed position, must be verified closed during each cold shutdown, except no more frequently than once every 92 days.
The licensee has requested that " main steam valve vaults" be added, which would lengthen the surveillance frequency from a 31 day interval to a cold shutdown interval (and no more frequent than 92 days) for inspection of components located in this area.
The valves located inside the main steam valve vaults that would be affected by the extended interval are various drain valves and test connections within the containment isolation boundary for the main steam and feedwater systems.
The valves are locked, sealed, or otherwise secured.
Because of the process fluid in these lines, any non-isolated line would become obvious because of the resulting influx of steam into the area, which would be detected either by ENCLOSURE 3 9412010144 941122 PDR ADOCK 05000327 P
e 1
. noting an increasing temperature indication for the valve vaults or by visual indication of steam escaping from the vents in the valve vault roof.
The main steam valve vaults contain areas of high temperature, significant personnel hazards, and significant physical equipment congestion.
Atmospheric temperature may reach 135'F in certain areas of the room.
Therefore, inspection of valves located in the valve vaults represents a significant personnel hazard.
For the same reasons, the rooms are very low traffic areas, even though there are doors on opposite sides of the room.
The physical congestion (including valves, piping, structural steel, and platforms) between the doors makes the use of the room impractical as a pathway to another destination.
As a result, passage through the valve vaults is very low.
Therefore, it is unlikely that a valve in this area that.s relied on to maintain containment integrity would become misaligned. A visual inspection of the rooms is performed by an auxiliary unit operator once per shift.
Because of the environmental conditions in the general area, certain administrative controls have been implemented by the licensee to protect personnel who must enter the area. An evaluation must be performed by the safety staff of all work activities during Modes 1, 2, or 3 that are to exceed 10 minutes in duration.
For valves in a high-heat stress area, the auxiliary operator performing the inspection would either take a second individual as an observer or would remain in constant contact with someone outside the room who could provide assistance in case of an emergency.
Implementation of this proposed amendment would reduce the number of times employees are required to enter the area and become exposed to the hazards in order to perform the surveillance test.
It is unlikely the position of the containment components would be changed accidently since the valve vaults are not in high traffic areas due to administrative controls and the physical condition of the areas preclude unnecessary personnel entry. Any change to the status of the containment components or small steam leaks, should they occur, would be readily detected.
Therefore, the staff has determined the proposed change to include the main steam valve vaults in the areas that are excluded from the containment integrity surveillance requirement verification that is performed every 31 hard days, and include it in the footnote to the requirement so that the test is performed every cold shutdown (but not more frequently than once per 92 days) acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Tennessee State official was notified of the proposed issuance of the amendment.
The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no
s
. significant increo.
individual or cumulative occupational radiation d
exposure. The Comm.... ion has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (59 FR 51630). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
5.0 CONCLUSION
The Commission has concluded, based on the considcrations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
)
Principal Contributor: David E. LaBarge Dated: November 22, 1994 a
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Mr. 0 liver D. Kingsley, Jr.
SEQUOYAH NUCLEAR PLANT Tennessee Valley Authority cc:
Mr. Craven Crowell, Chairman Mr. Roger W. Huston, Manager Tennessee Valley Authority Nuclear Licensing and ET 12A Regulatory Affairs 400 West Summit Hill Drive Tennessee Valley Authority Knoxville, TN 37902 4G Blue Ridge 1101 Market Street Mr. W. H. Kennoy, Director Chattanooga, TN 37402-2801 Tennessee Valley Authority ET 12A Mr. Ralph H. Shell 400 West Summit Hill Drive Site Licensing Manager Knoxville, TN 37902 Sequoyah Nuclear Plant Tennessee Valley Authority Mr. Johnny H. Hayes, Director P.O. Box 2000 Tennessee Valley Authority Soddy Daisy, TN 37379 ET 12A 400 West Summit Hill Drive TVA Representative Knoxville, TN 37902 Tennessee Valley Authority 11921 Rockville Pike Mr. O. J. Zeringue, Sr. Vice President Suite 402 Nuclear Operations Rockville, MD 20852 Tennessee Valley Authority 3B Lookout Place Regional Administrator 1101 Market Street U.S. Nuclear Regulatory Commission Chattanooga, TN 37402-2801 Region II 101 Marietta Street, NW., Suite 2900 Dr. Mark 0. Medford, Vice President Atlanta, GA 30323 Engineering & Technical Services Tennessee Valley Authority Mr. William E. Holland 3B Lookout Place Senior Resident Inspector 1101 Market Street Sequoyah Nuclear Plant Chattanooga, TN 37402-2801 U.S. Nuclear Regulato Commission 2600 Igou Ferry Road Mr. D. E. Nunn, Vice President Soddy Daisy, TN 37379 New Plant Completion Tennessee Valley Authority Mr. Michael H. Mobley, Director 3B Lookout Place Division of Radiclogical Health 1101 Market Street 3rd Floor, L and C Annex Chattanooga, TN 37402-2801 401 Church Street Nashville, TN 37243-1532 Site Vice President Sequoyah Nuclear Plant County Judge Tennessee Valley Authority Hamilton County Courthouse P.O. Box 2000 Chattanooga, TN 37402 Soddy, Daisy, TN 37379 General Counsel Tennessee Valley Authority ET 11H 400 West Summit Hill Drive Knoxville, TN 37902