ML20211F307

Forwards marked-up Rev to Tech Spec 3/4.7.7 Re Auxiliary Bldg Filtered Exhaust Sys,As Suppl to 860409 Tech Spec Change Request.Rev Deletes Proposed Action When Both Trains of Sys Inoperable & Complies W/Intent of NUREG-0452

ML20211F307
Person / Time
Site:	Catawba
Issue date:	02/13/1987
From:	Tucker H DUKE POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-0452, RTR-NUREG-452 NUDOCS 8702250040
Download: ML20211F307 (4)

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DUKE POWER GOMPAhT P.O. BOX 33189 CHARLOTTE, N.O. 28242 HAL B. TUCKER TELEPHONE vuos russananT (704) GN531 NUCLEAR PRODUCTION February 13, 1987 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555

Subject:

Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 Technical Specification 3/4.7 . 7 Auxiliary Building Filtered Exhaust System Gentlemen:

This letter supplements my letter of April 9, 1986, and contains clarification to the requested change to Technical Specification 3/4.7.7.

The attached markup of the Catawba Units 1 and 2 Technical Specification differs from the previous submittal only in that the proposed action when both trains of the Auxiliary Building Filtered Exhaust System is inoperable has been deleted.

Therefore, the attached markup of the Catawba Specification provides a more conservative change and is in compliance with the intent of NUREG-0452, Standard Technical Specifications for Westinghouse Pressurized Water Reactors.

As this request is a supplement to my April 9,1986 letter, no additional fee is required to be submitted.

Very truly yours, Hal B. Tucker RWO/15/sbn Attachment

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N00 0702250040 870213 PDR yg P

ADOCK 05000413 ,

PDR A

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+- U. S. Nucl0sr Regulct:ry Connicaica February 13, 1987 Page Two xc: Dr. J. Nelson Grace, Regional Administration U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. P. H. Skinner NRC Resident Inspector Catawba Nuclear Station Mr. Heyward Shealy, Chief Bureau of Radiological Health South Carolina Department of Health &

Environmental Control 2600 Bull Street Columbia, South Carolina 29201 M&M Nuclear Consultants 1221 Avenue of the Americas New York, New York 10020 American Nuclear Insurers e/o Dottie Sherman, ANI Library The Exchange, Suite 245 270 Farmington Avenue Farmington, CT 06032 INPO Records Center Suite 1500 1100 Circle 75 Parkway Atlanta, Georgia 30339

PLANT SYSTEMS 3/4.7.7 AUXILIARY BUILDING FILTERED EXHAUST SYSTEM LIMITING CONDITION FOR OPERATION

%o rnJapen/ cat drains af 3.7.7 yhe Auxiliary Building Filtered Exhaust System shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION: j p one.

With[heAuxiliaryBuildingFilteredExhaustSysteminoperable,restorethe inoperable :y:"- to OPERABLE status within _^ i. . or be in at least HOT STANOBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS Euh %;n of T)1e Auxiliary Building Filtered Exhaust System shall be demonstrated 4.7.7[CPERABLE:

a. At least once per 31 days by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 10 continuous hours with the heaters operating;

b. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical release in any ventilation zone

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communicating with the system by:

1) Verifying that the cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than 1% (Unit 1), 0.05% (Unit 2) and uses the test proce-dure guidance in Regulatory Positions C.5.a, C.5.c, and C.5.d*

of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 30,000 cfm t 10%;

2) Verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accor-l dance with Regulatory Position C.6.b of Regulatory Guide 1.52, l

Revision 2, March 1978, meets the laboratory testing criteria l of Regulatory Position C.6.a of Regulatory Guide 1.52, Revi-sion 2, March 1978, for a methyl iodide penetration of less than 1%; and i.

• The requirement for reducing refrigerant concentration to 0.01 ppm may be satisfied by operating the. system for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with heaters on and operating.

CATAWBA - UNITS 1 & 2 3/4 7-17 1 -. --- -. _ . - -_- _ _ - . . - - -__. - - - .-._ -

2 PLANT SYSTEMS BASES 3/4.7.7 AUXILIARY BUILDING FILTERED EXHAUST SYSTEM The OPERABILITY of the Auxiliary Building Filtered Exhaust System ensures that radioactive materials leaking from the ECCS equipment within the auxiliary building following a LOCA are filtered prior to reaching the environment.

Operation of the system with the heaters operating to maintain low humidity l using automatic control for at least 10 continuous hours in a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters.

The operation of this system and the resultant effect on offsite dosage calcu-lations wa eeeemed in the safety analyses. ANSI N510-1980 will be used as a procedura _uide for surveillance testing.

not en ueM b hoew, b opaden af h spb col A 3/4.7.8 SNUBBERS "5M $84 m Oc #C haD M" " M "5 was a mmd m N %W Sa.,4dE G -" S 4 -

All snubbers are required OPERA 8LE to ensure that the structural integrity of the Reactor Coolant System and all other safety-related systems is main

• tained during and following a seismic or other event initiating dynamic loads.

Snubbers are classified and grouped by design and manufacturer but not by size. For example, mechanical snubbers utilizing the sa'me design features of the 2-kip,10-kip, and 100-kip capacity manufactured by Company "A" are of the same type. The same design mechanical snubbers manufactured by Company "B" for the purposes of this Technical Specification would be of a different type, as would hydraulic snubbers from either manufacturer.

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' A list of individual snubbers with detailed information of snubber location and size and of system affected shall be available at the plant in accordance with Section 50.71(c) of 10 CFR Part 50. The accessibility of each snubber shall be determined and approved by the Catawba Safety Review Group. The determination

shall be based upon the existing radiation levels and the expected time to per-form a visual inspection in each snubber location as well as other factors asso-ciated with accessibility during plant operations (e.g., temperature, atmosphere, location etc.), and the recommendations of Regulatory Guides 8.8 and 8.10. The addition or deletions of any hydraulic or mechanical snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.

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CATAWBA - UNITS 1 & 2 B 3/4 7-4

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