ML003670061
| ML003670061 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/23/1999 |
| From: | Labarge D NRC/NRR/DLPM/LPD2 |
| To: | Mccollum W Duke Energy Corp |
| References | |
| TAC MA6868, TAC MA6869, TAC MA6870 | |
| Download: ML003670061 (3) | |
Text
December 23, 1999 Mr. W. R. McCollum, Jr.
Vice President, Oconee Site Duke Energy Corporation P. 0. Box 1439 Seneca, SC 29679
SUBJECT:
OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 RE: EXEMPTION FROM 10 CFR 50, APPENDIX J REQUIREMENTS FOR AIR LOCK LEAKAGE TESTING (TAC NOS. MA6868, MA6869, AND MA6870)
Dear Mr. McCollum:
The Commission has approved the enclosed exemption from certain requirements of Title 10 of the Code of FederalRegulations (CFR), 10 CFR Part 50, Appendix J, Section III.D.2(b)(ii),
pursuant to 10 CFR Part 50.12. This action is in response to your application dated October 5, 1999, to allow performance of a containment air lock door seal leak test in lieu of a full pressure test at the Oconee Nuclear Station, Units 1, 2, and 3.
The exemption allows a pressure test of the containment air lock seals to fulfill the air lock testing requirements specified in 10 CFR Part 50, Appendix J, Section III.D.2(b)(ii) providing that no work is performed on the containment air locks that could affect air lock sealing capability during periods covered by the requirement.
A copy of the exemption has been forwarded to the Office of the Federal Register for publication.
Sincerely, Original signed by:
David E. LaBarge, Senior Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287 Distribution: HBerkow OGC Docket File DLaBarge GHill (6)
Enclosure:
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UNITED STATES
_- *NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 S* -December 23, 1999 Mr. W. R. McCollum, Jr.
Vice President, Oconee Site Duke Energy Corporation P. 0. Box 1439 Seneca, SC 29679
SUBJECT:
OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 RE: EXEMPTION FROM 10 CFR 50, APPENDIX J REQUIREMENTS FOR AIR LOCK LEAKAGE TESTING (TAC NOS. MA6868, MA6869, AND MA6870)
Dear Mr. McCollum:
The Commission has approved the enclosed exemption from certain requirements of Title 10 of the Code of FederalRegulations (CFR), 10 CFR Part 50, Appendix J, Section III.D.2(b)(ii),
pursuant to 10 CFR Part 50.12. This action is in response to your application dated October 5, 1999, to allow performance of a containment air lock door seal leak test in lieu of a full pressure test at the Oconee Nuclear Station, Units 1, 2, and 3.
The exemption allows a pressure test of the containment air lock seals to fulfill the air lock testing requirements specified in 10 CFR Part 50, Appendix J, Section III.D.2(b)(ii) providing that no work is performed on the containment air locks that could affect air lock sealing capability during periods covered by the requirement.
A copy of the exemption has been forwarded to the Office of the Federal Register for publication.
Since David E. LaBarge, Senior Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287
Enclosure:
Exemption cc w/encl: See next page
Oconee Nuclear Station cc:
Ms. Lisa F. Vaughn Mr. L. E. Nicholson Legal Department (PBO5E) Compliance Manager Duke Energy Corporation Duke Energy Corporation 422 South Church Street Oconee Nuclear Site Charlotte, North Carolina 28201-1006 7800 Rochester Highway Seneca, South Carolina 29672 Anne W. Cottingham, Esquire Winston and Strawn Ms. Karen E. Long 1400 L Street, NW Assistant Attorney General Washington, DC 20005 North Carolina Department of Justice Mr. Rick N. Edwards P. 0. Box 629 Framatome Technologies Raleigh, North Carolina 27602 Suite 525 1700 Rockville Pike L. A. Keller Rockville, Maryland 20852-1631 Manager - Nuclear Regulatory Licensing Manager, LIS Duke Energy Corporation NUS Corporation 526 South Church Street 2650 McCormick Drive, 3rd Floor Charlotte, North Carolina 28201-1006 Clearwater, Florida 34619-1035 Mr. Richard M. Fry, Director Senior Resident Inspector Division of Radiation Protection U. S. Nuclear Regulatory North Carolina Department of Commission Environment, Health, and 7812B Rochester Highway Natural Resources Seneca, South Carolina 29672 3825 Barrett Drive Raleigh, North Carolina 27609-7721 Virgil R. Autry, Director Division of Radioactive Waste Management Mr. Steven P. Shaver Bureau of Land and Waste Management Senior Sales Engineer Department of Health and Environmental Westinghouse Electric Company Control 5929 Carnegie Blvd.
2600 Bull Street Suite 500 Columbia, South Carolina 29201-1708 Charlotte, North Carolina 28209
7590-01 -P UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of )
)
DUKE ENERGY CORPORATION ) Docket Nos. 50-269, 50-270, and 50-287
)
(Oconee Nuclear Station, Units 1, 2, and 3))
EXEMPTION I.
The Duke Energy Corporation (Duke/the licensee) is the holder of Facility Operating License Nos. DPR-38, DPR-47, and DPR-55, that authorize operation of the Oconee Nuclear Station, Units 1, 2, and 3 (Oconee), respectively. The licenses provide, among other things, that the facilities are subject to all rules, regulations, and orders of the U.S. Nuclear Regulatory Commission (the Commission) now or hereafter in effect.
The facilities consist of three pressurized water reactors located on Duke's Oconee site in Seneca, Oconee County, South Carolina.
II.
Title 10 of the Code of FederalRegulations (10 CFR) Part 50, Appendix J, contains the following requirements:
- a. Section IlI.D.2(b)(i) requires that air locks be tested prior to initial fuel loading and at 6-month intervals thereafter at an internal pressure not less than Pa (the calculated peak containment internal pressure related to the design basis accident).
- b.Section III.D.2(b)(ii) requires that air locks opened during periods when containment integrity is not required shall be tested at the end of such periods at Pa'
- c. Section llI.D.2(b)(iii) requires that air locks opened during periods when containment integrity is required shall be tested within 3 days after being opened.
For air locks opened more frequently than once every 3 days, the air lock shall be tested at least once every 3 days during the period of frequent openings. For air lock doors having testable seals, testing the seals fulfills the 3-day test requirement.
Ill.
The proposed action is in accordance with the licensee's application for exemption contained in a submittal dated October 5, 1999.
Whenever the plant is in cold shutdown (Mode 5) or refueling (Mode 6), containment integrity is not required. However, if an airlock is opened when in Modes 5 or 6 (which is usually the case), 10 CFR 50, Appendix J, Section Ill.D.2(b)(ii) requires that an overall air lock leakage test at not less than Pa be performed before plant heatup and startup (i.e., before Mode 4 is entered). The licensee has requested an exemption that would allow this test requirement to be met by performing an air lock door seal leakage test per 10 CFR 50, Appendix J, Section III.D.(b)(iii) during plant startup prior to entering Mode 4 if no maintenance has been performed on the air lock that could affect its sealing capability. If maintenance has been performed that could affect its sealing capability, an overall air lock leakage test per 10 CFR 50, Appendix J, Section III.D.2(b)(ii) would be necessary prior to establishing containment integrity.
The existing air lock doors are designed so that the air lock pressure test can only be performed after a strongback (structural bracing) has been installed on the inner door, since the pressure used to perform the test is opposite that of accident pressure and would tend to unseat the door. Performing the full air lock test in accordance with the present requirements
takes approximately 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, since it requires installation of the strongback, performing the test, and removing the strongback. During the test, access through the air lock is prohibited, which, therefore, requires evacuation of personnel from the containment or the personnel must remain inside the containment during the test until Mode 4 is reached. The licensee has determined that pressurizing the volume between the seals to 60 pounds per square inch gauge pressure after each opening, and prior to establishing containment integrity, provides the necessary surveillance to ensure the sealing capability of the door seals.
If the periodic 6-month test of 10 CFR 50, Appendix J, Section III.D.(b)(i) and the test required by 10 CFR 50, Appendix J, Section III.D.(b)(iii) are current, no maintenance has been performed on the air lock that could affect its sealing capability, and the air lock is properly sealed as determined by the seal test, there is no reason to expect that the air lock will leak just because it has been opened in Modes 5 or 6. Therefore, there is no impact on plant operation or safety. In addition, due to the design of the air lock, the 6-month test should detect air lock deterioration.
IV.
Pursuant to 10 CFR 50.12, the Commission may, upon application by any interested person or upon its own initiative, grant exemptions from the requirements of 10 CFR Part 50, when (1) the exemptions are authorized by law, will not present an undue risk to public health or safety, and are consistent with the common defense and security; and (2) when special circumstances are present. This is also consistent with the determination that the staff has reached for other licensees under similar conditions based on the same considerations.
Accordingly, the staff concludes that the licensee's proposed approach of substituting the 3-day seal leakage test requirements of 10 CFR 50, Appendix J, Section IIl.D.(b)(iii) for the full pressure test of 10 CFR 50, Appendix J, Section III.D.(b)(ii) is acceptable when no
maintenance that could affect the sealing capability has been performed on the air lock.
Whenever maintenance that could affect the sealing capability has been performed on the air lock, the full pressure test requirements of 10 CFR 50, Appendix J, Section III.D.(b)(ii) must still be met.
Therefore, the staff concludes that requesting the exemption under the special circumstances of 10 CFR 50.12(a)(2)(ii) is appropriate and that application of the regulation is not necessary to serve the underlying purpose of the rule. The underlying purpose of the rule is to ensure that: (a) leakage through the primary containment, and systems and components penetrating the primary containment, does not exceed the allowable leakage rate values specified in the Technical Specifications or associated Bases; and (b) periodic surveillance of containment penetrations and isolation valves, and systems and components penetrating the containment, is performed so that proper maintenance and repairs are made during the service life of the containment.
V.
Accordingly, the Commission has determined that, pursuant to 10 CFR 50.12(a), the exemption is authorized by law, will not endanger life or property or common defense and security, and is, otherwise, in the public interest. Therefore, the Commission hereby grants Duke an exemption from the requirements of 10 CFR Part 50, Appendix J, Section III.D.2(b)(ii) for containment air lock tests as described above, for the Oconee Nuclear Station, Units 1, 2, and 3.
Pursuant to 10 CFR 51.32, the Commission has determined that the granting of this exemption will not result in any significant effect on the quality of the human environment 64 FR 70072)
This exemption is effective upon issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Original signed by:
John A. Zwolinski, Director Division of Licensing Project Management Office of Nuclear Reactor Regulation Dated at Rockville, Maryland, this 23rd day of December 1999.
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Pursuant to 10 CFR 51.32, the Commission has determined that the granting of this exemption will not result in any significant effect on the quality of the human environment (64 FR 70072 ).
This exemption is effective upon issuance.
FOR THE NUCLEAR REGULATORY COMMISSION John A. Zwolinski, Director Division of Licensing Project Management Office of Nuclear Reactor Regulation Dated at Rockville, Maryland, this 23rd day of December 1999.