ML19340C728

Forwards Revision 3 of Response to NUREG-0578, TMI-2 Lessons Learned Task Force Status Rept & Short-term Recommendations. Revision Changes Response to Item 2.1.8a Re Improved post-accident Sampling

ML19340C728
Person / Time
Site:	Sequoyah
Issue date:	12/10/1980
From:	Mills L TENNESSEE VALLEY AUTHORITY
To:	Schwencer A Office of Nuclear Reactor Regulation
References
RTR-NUREG-0578, RTR-NUREG-578, TASK-2.B.1, TASK-TM NUDOCS 8012170306
Download: ML19340C728 (5)

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TENNESSEE VALLEY AUTHORITY CH ATTANOOG A, TENNESSEE 37401 400 Chestnut Street Tower II December 10, 1980 Director of Nuclear Reactor Regulation Attention : Mr. A. Schwencer, Chief Licensing Branch 'Jo. 2 Division of Licensing U.S. Nuclear Regulatory Co=ission Washington, DC 20555

Dear Mr. Schwencer:

In the Matter of the Application of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 Enclosed are ten (10) copies of revision 3 of TVA's response for Sequoyah Nuclear Plant to :;UREG-0578, TMI-2 Lessons Learned Task Force Status Report and Short Ter: Reco=endatiors. This revision changes TVA's response to item 2.1.8a, Improv3d Post-Accident Sa pling Capability, to state that pro-visions will be cade to take samples from the containment sucp.

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LIST CT REVISIONS 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, 1989, February 1, 1980, and April 2, 1980 Revisien 1, June 23, 1980 Incorporate revisions to the responses to item 2.1.4 Containment Isolation, and item 2.1.6b, Shielding Revisi n 2, July 11, 1980 Incorporate revisions to i+ec 2.1.6a as Appendices E and F, Leak Testing Procedures for the Waste Gas System and the Results of the Leak Reduction Program for Liquid and Gas Systems, respectively Revision 3, December 10, 1980 Revise the response to item 2.1.8a, Improved Post-Accident Sampling Capability, to state that provisions will be made to take samples from the containment sump l

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i December 10, 1980 1

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INSTRUCTION SHEET REVISION 3 Pages Removed Pages Inserted Front /Back. Front /Back.._

1/- rev. 2 1/- rev. 3 51/52 51/52 I

i December 10, 1980 r

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I!9 ROVED POST-ACCIDENT SAMPLING CAPABILITY - 2.1.8a SEQU0YAli NUCLEAR PLANT RESPONSE Su= mary

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A design and opera'tional review of the reactor cool' ant and containment atmosphere sampling systets and analysis facilities has been performed.

TVA expects to complete the necessary modifications in accordance with the schedules established by the NRC.

Response

A design and operational review of the reactor coolant sampling systems and analysis facilities has been performed. TVA expects to complete required modificatiens in accordance with the schedules established by the NRC provided that equipment procurement / installation conflicts are not encountered. These modilications will make provisions for sampling water from the reactor coolant syste= for the degraded accident condition.

The TVA review of reactor coolant sa=pling systems has determined that current facilities are not -adequate to sa:ple, handle, and analyze highly radioactive water and gas samples and that modification of existing facilities is impractical. As a result, TVA is 4orking with Oak Ridge National Laboratory (ORNL) to develop and design such a facility.

Until the design modifications are co=plete, precedures have been devised to evaluate the primary coolant system activity depending on the accessi-bility of the sampling stations for particular degraded conditions. Refer to Appendix 3 of TVA's response to NUREG-0578 for Sequoyah Technical Instructicn (TI) 66, Post Accident Sa=pling and Analysis Methods.

To enhance the capability at Sequoyah for post-LOCA sampling TVA will:

1. Make previsions for sampling water from the reactor coolant system and the containment sump for the degraded accident l

condition i 2. Install new lines with connections to the existing gaseous radia-l tien aampling system for use in sampling the containment at:cspiere for the degraded accident conditions 3 Route sample lines to a shielded sampling station in an accessible

, area and provide for taking samples which could be removed offsite l

for analysis Clarification Items A. TVA will provide the capability to obtain (within one hour) Reactor Coolant samples and containment air samples under accident conditions.

Refer to pages 52a through 52m for current sampling procedures.

I Revision 3, December 10, 1980 51 l

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B. Plant procedures for the handling and aalysis of samples, minor plant, modifications for taking samples, and a design review and procedu*ral modifications (as necessary) have been completed. Refer to Appendix B of TVA's response to NUREG 0578 for Technical Instruction 66, Post Accident Sampling and Analysis Methods. TVA will provide, as practical, onsite radiological and chemical analysis capacities in order to quantify the following:

1. core da= age (RES)

2. hydrogen level in containment

3. dissolved gases and boron content (RCS)

C. Provisions will be made:

1. to permit sampling uncer both positive and negative pressure.

2. for purging sample lines, for reducing platcou; in sample lines, for minimizing sample loss or distortion, for preventing blockage of sample lines, for appropriate disposal of samples, and for passive flow restrictions.

3. to qualify the sampling system to appropriate seismic and environmental requirc.nents.

D. The radiological sample analysis capability will include provisions to:

a. Identify and quantify isotopes to levels corresponding to the source terms given in item 2.1.6.b. The ability to dilute samples and to measure nuclide concentrations as low as 1 pCi/gm will be provided.

b. Restrict background levels in the health physics laboratory.

c. Maintain plant procedures to identify the analysis required, measurement techniques and provisions for reducing background.

E. The chemical analysis capability will consider the presence of the radiological source term indicated by the radiological analysis.

F. Procedural changes and plant modifications will be made to assure that radiation exposures are as low as reasonably achievable, TVA will ensure that these criteria are met using the criteria identified.

G. TVA will demonstrate the capability to obtain and analyze a sample containing radio isotopes according to the criteria discussed above.

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