ML19339D028

Forwards Response to NRC Position Re Seismic Qualification Review Team,Auxiliary Feedwater Interim Procedural Implementation,Containment Purge Seal Changeout & Purge Operation

ML19339D028
Person / Time
Site:	Farley
Issue date:	02/09/1981
From:	Clayton F ALABAMA POWER CO.
To:	Schwencer A Office of Nuclear Reactor Regulation
References
NUDOCS 8102170043
Download: ML19339D028 (6)

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Alabama Power Company a

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• 600 North 18th street Post Offica Bo2 2641 Birmingmam. Alacama 35291 Teiephone 205 250-1000 F. L CLAYTON, JR.

Senior vice President m

Alabama Power tre sootrem swinc sys>m February 9, 1981 Docket flo. 50-364 Director, fluclear Reactor Regulation U. S. fluclear Regulatory Comission Washington, D. C. 20555 Attention: Mr. A. T. Schwencer Gentlemen:

JOSEPH M. FARLEY NUCLEAR PLANT - UNIT 2 RESPONSE TO NRC STAFF POSITIONS Enclosed, as requested by the NRC staff, are Alabama Power Company's responses to NRC staff position concerning Sc'smic Qualification Review Team (SQRT) review (review item 4), auxiliary feedwater interim procedural inplementation (review item 10), containment purge seal changeout (review item 1.1), and purge operation (review item 16). These responses have been

' discussed with the flRC staff and are believed by Alabama Power Company to satisfy the f!RC positions.

If there are any questions, please contact us.

Yours very tr,u t / L, %u

. L. Claytor., Jr.

FLC/RLG:de Enclosures cc: fir. R. A. Thomas

!1r. G. F. Trowbridge Mr. L. L. Kintner Mr. W. H. Bradford g@[

Ii 81021700% e

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Seismic Qualification Review (SQRT)

Position The applicant has also provided information in their letters dated August 15 and October 6,1980 which clarifies the seismic qualification of the equipment identified during our plant site review, as described in our trip report. The applicant has also committed to complete the following modifications prior to full power operation of Farley 2:

1. Anchor the battery rack (service water building) to the wall as specified in the analysis report.

2. Mount the solenoid valves (river water building) directly to the seismic supports with suitable brackets, to assure that no natural frequencies exist below 20 Hz.

Response

1 The modifications to the solenoid valves in the river water have been completed. Final design and equipment are onsite and work is in progress on the service water building battery rack modification. This work

. will be completed by February 13, 1981.

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V AUXILIARY FEEDWATER CONTROL SYSTDI Position j

j _, During the first refueling outage for Farley Unit 2 and third

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refueling outage for Unit 1, the protection system logic will be modi-fied such that all automatic initiation signals for the AFW system

.I vill automatically open the motor driven pump discharge control valves regardless of the position of the valve operating mode switches. In the interim, the adminstrative controls for this system will be enhanced by revised unit operating procedures which include sign off actions for

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placing the system in the mode required for proper response.

Response

Alabama Power Company committed, in a letter from F. L. Clayton, Jr.

to R. L. Tedesco dated December 4,1980, to Laplementing the above stated modification or to implement an NRC staff approved alternate design pro-viding equivalent AFW initiation capability by the dates mentioned above.

Unit operating procedures have been revised to include sign off actions for placing the system in the proper response mode.

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' L Disc Seals for 48-Inch Purge and 18-Inch Minicurge Valves j Position Disc seals for the 48-inch purge and 13-inch ninipurge valves should

be replaced overy five years.

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l _ Response

] Henry Pratt recommends replacement of the disc seals on a regular basis with intervals not to exceed five years. This five-year replacement cycle is based on industry standards for minimizing maintenance work and associated equipment down time. Alabama Power Company will conform to the five-year replacement schedule for the disc seals.

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.* CONTAINMENT PURGE QUESTIONS i

References:

1) F. L. Clayton letter to A. Schwencer dated 9-30-80, Containment Purge System (Docket 50-364).

_ 2) F. L. Clayton letter to A. Schwencer dated 6-30-80, Containment Purge Valves (Docket 50-364).

3) F. L. Clayton letter to A. Schwencer dated 12.10-79,

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Containment Purge (Docket 50-348). '

4) F. L. Clayton letter to A. Schwencer dated 2-5-79, Containment Purging During Normal Plant Operation (Docket 50-348)/

NRC POSITION Verification that the three-inch vent valves satisfy the operability criteria set forth in Branch Technical Position CSB 6-4 or the Staff Interim Position of October 23, 1979:

RESPONSE

The three-inch vent valves are still in the conceptual design phase. It is our

, ntion to design these valves'to meet the essential requirements of BTP CSB NOTE: As a result of discussions with the NRC staff on February 4,1981, Alabama Power requests the option of installing an eight (8) inch purge / vent system

!~~ in lieu of a three (3) inch vent system for the long term solution of purging / venting the containment during normal plant operation. The eight (8) inch purge / vent system would consist of three (3) gate or globe valves in series for the containment supply and exhaust lines and the complete system would meet the current requirements of BTP CSB 6-4.

NRC POSITION Verification that the estimated amount of radioactivity released d'u ring the time required to close the purge system or vent line valve followin not cause the total offsite dose to exceed the 10 CFR Part 100 deline gui' g values:

a LOCA. does

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RESPONSE

Reference (4) provides the required information for the 18" mini-purge valves.

Since the results given in this reference assumed maximum flow conditions (density, temperature, pressure) out of the 18" line and since the 3" vent. lines tap into the same 18" line, no significant increase in flow, and therefore ho significant-increase in dose at the site boundary will be experienced out of the 18" line.

NRC POSITION The basis for the number of annual hours of purging and venting expected.

RESPONSE

The basis for continued operation of the mini-purge system until installation of the 3" vent valves is given in references (1), (2), (3), and (4).

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7 ' Containment Purge Questions - Page 2 NRC POSITION Verification that the forty-eight inch containment purge valves will be sealed closed during reactor operating conditions 1, 2, 3 and 4.

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See Reference (2) for this verification. .

NRC POSITION -

Provide justification for the number of hours the 18" purge lines will be used prior to installation of the 3" vent line.

RESPONSE

'See 3 above. -

NRC POSITION Provide number of hours and justification for use of 18" mini-purge lines after 3" valves are installed.

RESPONSE

The Farley Nuclear Plant 18" purge system has a containment removal half life of 4.68 hours7.87037e-4 days <br />0.0189 hours <br />1.124339e-4 weeks <br />2.5874e-5 months <br />. This removal half life requires that times on the order of days be used to purge the containment to MPC values for various noble gases assuming no purge prior to recognition that the containment entry was required. A time of 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> was based upon previously developed times for the main purge system using a historical study of actual Unit 1 entries.

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