ML20056C523

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Summary of 930602 Meeting W/Util Re Plant Proposal for Removing 2C Emergency Diesel Generator from TS as Part of Farley Implementation of Station Blackout Rule.List of Attendees Encl
ML20056C523
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 06/18/1993
From: Tim Reed
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 9306240415
Download: ML20056C523 (28)


Text

.. - -. . . - . .

i i  ?> NUCLEAR REGULATORY COMMISSION 5 WASHINGTON, D.C. 20666-0001 g

  1. June 18, 1993 Docket Nos. 50-348 and 50-364 LICENSEES: Southern Nuclear Operating Company (SNC)'

FACILITIES: Farley Nuclear Plant Units 1 and 2 SUBJECl:

SUMMARY

OF THE JUNE 2, 1993, MEETING WITH. SOUTHERN NUCLEAR- . o OPERATING COMPANY, INC., REGARDING THE STATION BLACK 0UT TECHNICAL SPECIFICATION PROPOSAL FOR JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 P

On June 2,1993, the NRC staff met with representatives of Southern Nuclear Operating Company, Inc., (SNC or the licensee) to discuss the-Joseph M. Farley Nuclear Plant, Units 1 and 2, (Farley) proposal for removing the 2C emergency..

diesel generator (EDG) from the Technical Specifications;(TS) as part of the '

Farley implementation of the Station Blackout Rule.

Meeting attendees are listed in Enclosure 1. The handouts distributed during the meeting are provided as Enclosure 2.

A SNC representative opened the meeting and provided an overview of both:the '

Farley proposal to remove the '2C EDG from the TS and the associated station  ;

blackout (SBO) modifications that Farley plans to implement in the upcoming-outage on Unit 2. '

The licensee provided a chronology and history of issues associated with the Farley electrical system. This included a discussion.of previous TS changes -l involving the Farley EDGs. '

The licensee presented the design basis of the Farley electrical system and its capability to mitigate the loss of offsite. power (LOSP), LOSP and concurrent loss-of-coolant accident (LOCA), and SB0. This discussion highlighted the differences between the current configuration and the configuration following the SB0 modifications planned for the' upcoming Unit 2 outage (September). It is Farley's view that following the planned modifications, less manual operator actions will be required to utilize the 2C EDG for both an SB0 and for an event'that is-beyond the design basis (basis for the Farley 10-day allowed outage time). Following-the planned modifications, the operator needs only to identify the SB0 unit, switch.(in the control room) the EDG to the SB0 unit, and press the start button. The remainder of t% response to the SB0-(regarding the reestablishment of AC power) is fully automatic. "

The central issue discussed.during the meeting involved the controls ..

(maintenance, surveillance, and actions taken if 2C .is not. inservice) that .

would be placed on the 2C EDG if it is removed from the Farley'TS as proposed. ,

9306240415 930618 PDR P

ADOCK 05000340- h#hb 3' 5 W"" ' " ~"# -

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June 18, 1993 I

At this time, the license has not determined the specific document that will contain the EDG 2C maintenance procedures (FSAR or a separate document). The staff's concern is to assure that the 2C EDG is maintained as a IE machine and that it is both reliable and available.

A suggestion was made that Farley could supplement their current proposal to:

(1) place a line item in the administrative controls portion of the TS, (2) remove the 2C EDG TS controls and place them either in the FSAR or another document (controlled by 10 CFR 50.59), and (3) ensure that 2C is not removed for more than 10-days at a time without first notifying the staff (part of the line item administrative TS change). Farley would need to supplement their current TS request with the additional administrative line item change.

If there are questions regarding the meeting, I can be contacted at 301-504-1463.

ORIGINAL SIGNED BY:

Timothy A. Reed, Senior Project Manager Project Directorate 11-1 Division of Reactor Projects - I/II

Enclosures:

1. List of Attendees
2. Meeting Handouts cc w/ enclosures:

See next page

_^

OFFICE LA:PD2((bkPE PM/[IjhPE AD:PD21_:DRPE NAME PDAn[eNn TANd:tmw SSBajwNI t DATE 06//1/93 06)' h/93 06/ 19I /93 Document Name: FARSBO.MTS l

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Joseph M. Farley Nuclear Plant-cc:

Mr. R. D. Hill, Jr. State Health Officer General' Manager -- Farley Nuclear Plant Alabama Department of Public Health Southern Nuclear Operating Co., Inc. 434_ Monroe Street Post Office Box 470 Montgomery, Alabama 36130-1701 Ashford, Alabama 36312 Chairman Mr B. L. Moore, licensing Manager Houston County Commission Southern Nuclear Operating Co., Inc. Post Office Box 6406.

Post Office Box 1295 Dothan, Alabama 36302 Birmingham, Alabama 35201-1295 Regional Administrator, Region II James H. Miller, III, Esquire U. S. Nuclear Regulatory Commission Balch and Bingham Law Firm 101 Marietta St., N.W., Ste. 2900 Post Office Box 306 Atlanta,-Georgia 30323 1710 Sixth Avenue North Birmingham, Alabama 35201 Resident Inspector U.S. Nuclear Regulatory Commission Mr. J. D. Woodard Post Office Box 24 - Route 2 Executive Vice President Columbia, Alabama 36319 Southern Nuclear Operating Co., Inc.

Post Office Box 1295 Birmingham, Alabama 35201-1295 O

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DISTRIBUTION:

Enclosure 1 and 2:

IDocket Eilesib NRC/ Local PDRs PD 1I-1 Rdng. File T. Reed E. Herschoff, R-II Enclosure 1:

T. Murley/F. Miraglia 12-G-18 J. Partlow. 12-G-18 .

S. Varga G. Lainas S. Bajwa P. Anderson P. Gill 7-E-4 E. Weiss 7-E-4 F. Ashe 7-E-4 D. Nguyen 7-E-4 A.' Pal 7-E-4 C. Berlinger 7-E-4 E. Jordan MNBB 3701 OGC ACRS (10)

L. Plisco, EDO 17-G-21 E.~Merschoff, R-II cc: Licensee & Service List ,

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i

. -4 ENCLOSURE 1  :

i SOUTHERN NUCLEAR OPERATING' COMPANY /NRC MEETING .

1 REGARDING' STATION BLACK 0UT TECHNICAL SPECIFICATIONS-JUNE 2, 1993 ,

LIST OF ATTENDEES NAME ORGANIZATION Tim Reed NRR/PD II-1/Farley' PM =

S. Singh Bajwa NRR/PD:II-1/APD: -

Gus LainasL NRR/AD R-II.  :

Paul Gill .NRR/EELB-Eric Weiss NRR/EELB Frank'Ashe NRR/EELB _

Amar N. Pal NRR/DE/EELB. .

Duc Nguyen. NRR/DE/EELB .

Misu Iosefsohn Bechtel/Farley Electrica1L Jerry G. Sims SNC/ Nuclear _ Engineering - -

Scott Fulmer 'SNC/ Operations.

, Brad Moore SNC/ Licensing

' Brian Whitley SNC/ Licensing Dave Morey SNC/ Nuclear. Support Carl H., Berlinger NRC/DE/SELB

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ENCLOSURE 2L e

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JUNE 2,1993-MEETING BETWEEN SOUTHERN NUCLEAR OPERATING COMPANY AND THE-

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NUCLEAR REGULATORY COMMISSION CONCERNING THELFARLEY NUCLEAR PLANT ELECTRICAL SYSTEM DESIGN 4

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- .. _ . - .- - - a . . _ .

l AGENDA FOR THE JUNE 2,1993 MEETING TO i DISCUSS.THE FARLEY NUCLEAR PLANT  ;

ELECTRICAL SYSTEM DESIGN l

l. Introduction Brad Moore i

ll. Chronology of Electrical Brian Whitley.

System T. S. Issue 111. Review of Present Electrical Brad Moore

System Design

IV. Impacts of Station Blackout Brad Moore l Modificaticns i

V. Conclusion Dave Morey l

-- r

i I

PREVIOUS T.S. ISSUES 1

ISSUE Annual maintenance could last up to 10 days without declaring an EDG inoperable.

RESOLUTION Clarified the T.S. to eliminate the inappropriate wording.

ISSUE 18 day AOT for an EDG.

RESOLUTION-Reduced AOT to 10 days for an EDG.

ISSUE Operating mode changes can be made with one EDG inoperable.

BESOLUTION Maintained allowance to change operating modes with an inoperable EDG.

ISSUE 7 day AOT for an offsite circuit.

RESOLUTION Reduced AOT to 72~ hours for an offsite circuit.

s

PROPOSED T.S. CHANGES.

DUE TO SBO MODIFICATIONS

= DELETE ALL REFERENCES TO EDG 2C FROM T.S. SINCE IT WILL BECOME THE SBO ALTERNATE AC SOURCE.

= IMPLEMENT A PROGRAM TO ENSURE A RELIABILITY FACTOR OF O.95 FOR-EDG 2C. ,

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SNC'S UNDERSTANDING OF REMAINING T.S. ISSUES 4

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- BY DELETING EDG 2C FROM THE T.S., THE i FLEXIBILITY ARGUMENT PRESENTED IN-SUPPORT OF THE 10 DAY AOT FOR AN EDG AND THE ALLOWANCE TO CHANGE  :

OPERAflNG MODES WITH ONE EDG INOPERABLE ARE NO LONGER VALID.

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- WITHOUT AN AUTOMATIC START  !

FEATURE, NO CREDIT TOWARDS l ADDITIONAL FLEXIBILITY CAN BE GIVEN FOR EDG 2C.

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4-.m~+ -- ,-g, r- , r- y. = q~-- v.

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PRESENT DIESEL: GENERATOR ARRANGEMENT L

P s $ 4 230 KV 230 KV SWING SWING DEDICATED SHARED soo soo J( )( soo soa i

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SIMPLIFIED SCHEMATIC

. FIGURE ' 1

EMERGENCY AC POWER DISTRIBUTION SYSTEM 230 KV 230 KV 230 KV 230 KV

)N )N ]N AN X pM R XxMl R

  1. fhR XX R

( *( "C ( ( *( "C C 1H 1K 1F 1G >

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1B 1-2A FIGURE 2

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J l I _.__J I I 4 UNIT 1 >< UNIT 2 >

PRESENT DIESEL' GENERATOR ARRANGEMENT FIGURE 3

9 4

THE DESIGN BASIS FOR FARLEY NUCLEAR PLANT

= DUAL UNIT LOSS OF OFFSITE POWER Coincident with a

= SINGLE UNIT LOSS OF COOLANT ACCIDENT Assuming a_

= SINGLE FAILURE OF AN ACTIVE COMPONENT l

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PRESENT DIESEL GENERATOR ARRANGEMENT RUN RUN V

V, '

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l r l:

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FIGURE 4

e PRESENT DIESEL GENERATOR ARRANGEMENT l .

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FIGURE 5

t PRESENT DIESEL GENERATOR ARRANGEMENT RUN RUN RUN l'

I RUN f RUN 1C h --

U nummmmes l

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DUAL UNIT LOSP (ALL D/G's AVAILABLE)

FIGURE 6

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PRESENT DIESEL GENERATOR ARRANGEMENT RUN RUN RUN 1 RUN I 1-2A RUN h

or  ;

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< UNIT 1 > d. UNIT 2 >

DUAL UNIT LOSP, SI UNIT 1 (ALL D/G's AVAILABLE)

FIGURE 7

PRESENT DIESEL GENERATOR ARRANGEMENT RUN RUN RUN l'

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4 UNIT 1 >< UNIT 2 >

DUAL UNIT LOSP, SI UNIT 2 (ALL D/G's AVAILABLE)

FIGURE 8

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' FIGURE 9

SBO DESIGN BASIS ,

. SINGLE UNIT EVENT

. LOSS OF OFFSITE POWER TO BOTH UNITS

. LOSS OF ALL (3) EDG'S TO THE BLACKOUT UNIT

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DIESEL GENERATOR ARRANGEMENT FOLLOWING SBO MODIFICATIONS RUN RUN i l L l 1 l G g> H 55"

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< UNIT 1 >< UNIT 2 >

LOSP UNIT 1 (ALL D/G's AVAILABLE)

FIGURE 10

DIESEL GENERATOR ARRANGEMENT l . FOLLOWING SBO MODIFICATIONS RUN RUN i 1 1  ! 1 V U 855 V

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( UNIT 1 >< UNIT ': >

LOSP UNIT 2 (ALL D/G's AVAILABLE)

FIGURE 11

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DIESEL GENERATOR ARRANGEMENT FOLLOWING SBO MODIFICATIONS RUN RUN RUN 1-#

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a l < UNIT 1 > < UNIT 2 >  !

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! DUAL UNIT LOSP (ALL D/G's AVAILABLE) i- FIGURE 12 '

.__ _- . _ _ . - - . - . - ._ _ . - ~ . - ~ . . _ - .. -- _ _ _ . . _ _ _ _ _ _ _ _ _ - - - -

L .

i DIESEL GENERATOR ARRANGEMENT l FOLLOWING SBO MODIFICATIONS-

!- RUN RUN RUN IO g< J l [","" <J l

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< UNIT 1 ' D < UNIT 2 > j I

DUAL UNIT LOSP, SI. UNIT 1 (ALL D/G's. AVAILABLE);

FIGURE 13

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DIESEL GENERATOR ARRANGEMENT FOLLOWING SBO MODIFICATIONS RUN RUN RUN

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DUAL UNIT LOSP, SI UNIT 2 (ALL D/G's AVAILABLE)

- FIGURE 14

Fall Fall RUN Fall

' l I I RUN I l j

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EME EE E M E EbfEu li d s:m*L E M E E E E M E as:A; 5;. ~ mm

, < UNIT 1 >< UNIT 2 >

DIESEL GENERATOR ALIGNMENT DURING UNIT 1 SBO FIGURE 15

' RUN Fall

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Fall Fall i l T

k L k

RUN i

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i DIESEL GENERATOR ALIGNMENT DURING UNIT 2 SBO FIGURE 16

RUN Fall Fall Fall i P. U N l Vl i hU I I 1H 1K 1F 1G it 0 2H 2K 2F ?ll '

E E EE E <EbilmhG Ea wu'sa E E EE E E udRd ,. .a. ,

< UNIT 1 >< UNIT 2 >

l DIESEL GENERATOR ALIGNMENT DURING UNIT 2 SBO FIGURE .16

_ - _ _ _ _ __ _ _. - . - _ _ _ _ . - - - , _ - _ . __ __---___._ __ - . .- - . . . _ . . - _ _ - . . _ _ . _ _ _ _ _ _ _ _ _ _