ML19320B973
| ML19320B973 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 07/11/1980 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19320B974 | List: |
| References | |
| RTR-NUREG-0578, RTR-NUREG-578 NUDOCS 8007150571 | |
| Download: ML19320B973 (6) | |
Text
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TENNESZEE VALLEY AUTHORITY
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CH ATTANOO 2 A7TEr'.N f.22 EE 374o1 400 Chestnut Street Tower II 1
July 11, 1980 Director of Nuclear Reactor Regulation Attention:
Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U.S. Nuclear Re ulatory Commission 1
Washington, DC 20555
Dear Mr. Schwencer:
In the Matter of the Application of
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Docket Nos. 50-327 Tennessee Valley Authority
)
50-328 Enclosed are ten (10) copies of revision 2 of TVA's response for Sequoyah Nuclear Plant to NUREG 0578, TMI-2 Lessons Learned Task Force Status Report and Short Term Recommendations, Item 2.1.6a.
Revision 2 incorporates the leak testing procedures for the waste gas system (Appendix E) and the results of the leak reduction program for liquid and gas systems (Appendix F).
For your convenience, instructions are enclosed for incorporating these revisions into TVA's response to NUREG 0578'for Sequoyah Nuclear Plant which was transmitted by my letter to you dated i
July 3, 1980.
If you have any questions, please get in touch with D. L. Lambert at FTS 857-2581.
Very truly yours, TENNESSEE VALLEY AUTHORITY y.
L. M. Mills, Manager Nuclear Regulation and Safety Enclosure (10) e An Equal Opportunity Employer 80071505?/
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LIST OF REVISIONS k
Revision 0 Reprint document to consolidate letters to NRC dated October 31, 1979, November 21, 1979, January 11, 1980, January 17, 1980, January 18, 1980, January 25, 1980, February 1, 1980, and April 2, 1980 Revision 1, June 23, 1980 Incorporate revisions to the resoonses to item 2.1.4, Containment Isolation, and item 2.1.6b, Shielding.
Revision 2, July 11, 1980 Incorporate revisions to item 2.1.6a as Appendices E and F, Leak Testing Procedures For The Uaste Gas System and The Results Of The Leak Reduction Program For Liquid And Gas Systens, respectively O
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July 11, 1980 i
6 SYSTEMS INTEGRITY FOR HIGH RADIDAGTIVITY SECTION 2.1.6.a SEQUOYAH UUCLEAR PLANT RESPONSE
SUMMARY
TVA has investigated practical leakage reduction measures on systems which may contain radioactive fluids.
Procedures for reducing and quantifying leakage from liquid systems are presently in the review and approval cycle. These procedures will be submitted for NRC review.
RESPONSE
Plant design was reviewed to evaluate ways to minimize radioactive fluid leakage.
Plant systems that were reviewed included RHR, contain-ment spray, safety injection (recirculation mode), CVC, sampling, and waste disposal.
The examination included valve stem packing lankoffs, rotating seals, gasket connections, vents, and drains.
As a result of the review, a second pressure boundary will be incorporated on about twenty vents and drains found on pump suction lines and pump casings.
The second pressure boundary will be a second valve in most cases and an occasional blind flange.
An additional review was conducted with regard to the North Anna 1 incident and no similar release path was found.
The Sequoyah design routes the overpressure relief from the volume control tank to the pressurizer relief tank. At Sequoyah all relief paths from high pressure systems vent back into containment to the pressurizer relief tank. All tanks containing radioactivity in the radwaste system and the CVCS vent to a contained release path which is continuously monitored.
TVA will identify the above systems that may be leak checked and will implement a periodic leak check program on these systems.
System
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leakages will be reported to the NRC.
Procedures for reducing and quantifying leakage from liquid systems have been implemented. Appendix D to TVA's Response to NUREG 0578 for Sequoyah Nuclear Plant contains these procedures. These procedures were written in compliance with the guidelines listed below.
1.
Visual inspection with the system in operation is required.
2.
Closed loop systems, such as component cooling water, will not be inspected.
3.
Inspection will be performed quarterly except where accessibility is limited by radiation exposure.
These systems or partions of a system will be inspected during hot shutdown or other periods of accessibility.
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4.
Leakage will be quantified and specifically located by valve number pump flange or other similar means.
y 5.
Leakages will require immediate attention. All leakage identified will be " tracked" in plant until the leakage is stopped or controlled (i.e., normal pump seal leakage per manufacturer's spec).
6.
Leakage for each quarterly test will be reported on an annual basis to NRC.
The systems identified for leakage checks are listed below, a.
Safety Injection b.
RHR d.
Equipment and Flo'or Drain Systems (Primary Containment) e.
- Chemical and Volume Control System f.
Sampling
- Not required quarterly due to radiation exposure Procedures for reducing leakage from gaseous systems are based on the surveillance and inservice testing programs.
Identification of gaseous leakage is accomplished in response to any alarm from area radiation dectectors.
Leakages will require immediate attention.
All gaseous leakages will be " tracked" and be controlled. The leak testing preaedures for the waste gas systen are in Appendix E.
The results of the Icak reduction program for liquid and gas systens k
are in appendix F.
CLARIFICATION ITEMS Refer to response above.
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Revision 2, July 11,1980 8
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