ML20140H687

Forwards Copy of Farley Revised TS Bases Pages B 3/4 1-3 for Units 1 & 2 Dated to Correspond to Issue Date of Ltr

ML20140H687
Person / Time
Site:	Farley
Issue date:	06/16/1997
From:	Jacob Zimmerman NRC (Affiliation Not Assigned)
To:	Dennis Morey SOUTHERN NUCLEAR OPERATING CO.
References
TAC-M97245, TAC-M97246, NUDOCS 9706180411
Download: ML20140H687 (6)

Text

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y i UNITED STATES g j NUCLEAR REGULATORY COMMISSION l

o WASHINGTON D.C. 20066 4 001

% June 16, 1997 Mr. D. N. Morey

Vice President - Farley Project l Southern Nuclear Operating l Company, Inc.

Post Office Box 1295 l Birmingham, Alabama 35201-1295 t

SUBJECT:

PROPOSED REVISION TO TECHNICAL SPECIFICATION BASES FOR JOSEPH M.

FARLEY NUCLEAR PLANT, UNITS 1 AND 2 (TAC NOS. M97245 AND M97246)

Dear Mr. Morey:

By letter dated May 27, 1997, Southern Nuclear Operating Company, Inc. (SNC) provided the Nuclear Regulatory Commission's (NRC's) staff revised pages for Technical Specification (TS) Bases Section 3/4.1.2 for the Joseph M. Farley Nuclear Plant, Units 1 and 2. ,

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The revision to the Bases section was submitted to correct Units 1 and 2 TS Bases page B 3/4 1-3. The submittal correctly incorporates changes from the Core Operating Limits Report (COLR) TS amendment, which was issued by NRC l

1 letter dated March 25, 1997, and the elimination of Containment Spray Additive System by replacing it with Emergency Core Cooling System Recirculation Fluid pH Control System TS amendment, which was issued by NRC letter dated February 3, 1997.

Both TS amendments made changes to Farley Unit 1 TS Bases page B 3/41-3.

However, because of timing differences with submittal, issuance, and implementation, both TS amendmcnt changes were not incorporated into the last TS amendment that affected TS Bases page B 3/4 1-3. This same situation will occur for Unit 2 after the 12th refueling outage scheduled for spring 1998.

The Unit 2 elimination of Containment Spray Additive System TS Bases page j B 3/41-3 will be implemented after the Unit 2 COLR TS Bases page B 3/41-3 has been implemented.

For administrative purposes, the TS Bases change needs to be provided to the staff to enable all copies of the Farley TS to be updated in a consistent and i

1 timely fashion. l 1cCl%

1 9706180411 970616 PDR ADOCK 05000348 P PDR I

7 Mr. D. N. Morey June 16, 1997 Enclosed is a copy of the Farley revised TS Bases pages B 3/4 I-3 for Units 1 and 2 that have been dated to correspond to the issue date of this letter.

Sincerely, ORIGINAL SIGNED BY:

Jacob I. Zimerman, Project Manager Project Directorate 11-2 Division of Reactor Projects - I/II Office of F : tear Reactor Regulation Docket Nos. 50-348 at,d 50-364 DISTRIBtff f Docket File CGrimy;

Enclosure:

Units 1 and 2 Revised PUBLIC- ACRS Bases Section PDII 2 RF OGC G.H111(4) ,JJchnson, RII cc w/encic,: See next page PSkinner,RII SVarga

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l OFFICE PDII-h NII-2/LA PkI-3/D' NAME M rman LBerryNA Mow DATE [/d'4 /97 Nh/97 k//o/97 COPY /N)N0 fES)N0 YES[b) YES N0 YES N0

)0CUMENT NE: G:\fARLEY\B5M97245.CHG ~ OFFICIAL RECORD COPY 4

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i Mr. D. N. Morey Enclosed is a copy of the Farley revised TS C..'s pages B 3/41-3 for Units 1 and 2 that have been dated to correspond to the issue date of this letter. l l

Sincerely, l

. J J ob I. Z erman, Project Manager Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation  !

Docket Nos. 50-348 and 50-364

Enclosure:

Units 1 and 2 Revised Bases Section

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cc w/encls: See next page i

Joseph M. Farley Nuclear Plant l

Units I and 2 l I .

cc:

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Mr. R. D. Hill, Jr.

General Manager -

l Southern Nuclear Operating Company Post Office Box 470 Ashford, Alabama 36312 Mr. Mark Ajiuni, Licensing Manager

. Southern Nuclear Operating Company Post Office Box 1295 Birmingham, Alabama 35201-1295 l Mr. M. Stanford Blanton

! Balch and Bingham Law Firm Post Office Box 306 1710 Sixth Avenue North i Birmingham, Alabama 35201 Mr. J. D. Woodard Executive Vice President

, Southern Nuclear Operatir3 Company l Post Office Box 1295 Birmingham, Alabama 35201 State Health Officer Alabama Department of Public Health 434 Monroe Street Montgomery, Alabama 36130-1701 Chairman Houston County Commission Post Office Box 6406 '

Dothan, Alabama 36302 Regional Administrator, Region II .

U.S. Nuclear Regulatory Commission  !

Atlanta Federal Center 61 forsyth Street, S.W., Suite 23T85 Atlanta, Georgia 30303 ,

Resident Inspector U.S. Nuclear Regulatory Commission 7388 N. State Highway 95

! Columbia, Alabama 36319 ,

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REACTIVITY CONTROL SYSTEMS BASES I BORATION SYSTEMS (Continued)

With the RCS temperature below 200*F, one injection system is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity changes in the event the single injection system becomes inoperable.

The limitation for a maximum of one centrifugal charging pump to be OPERABLE and the Surveillance Requirement to verify all charging pumps except the required OPERABLE pump to be inoperable below 180*F provides assurance that a mass addition pressure transient can be relieved by the operation of a single RHR relief valve.

The boron capability required below 200'F is sufficient to provide a SHUTDOWN MARGIN as specified in the COLR after xenon decay and cooldown from 200'F to 140*F. This condition requires either 2,000 gallons of 7000 ppm borated water from the borie acid storage tanks or 7,750 gallons of 2300 ppm borated water from the refueling water storage tank.

The contained water volume limits include allowance for water not available because of discharge line location and other physical j characteristics.

The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 7.5 and 10.5 for the solution recirculated l within containment after a LOCA. This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.

i The OPERABILITY of one boron injection system during REFUELING ensures that this system is available for reactivity control while in MODE 6. j 3/4.1.3 MOVABLE CONTROL ASSEMBLIES

'se specifications of this section ensure that (1) acceptable power  !

distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is maintained, and (3) limit the potential effects of rod misalignment on associated accident analyses. OPERABILITY of the control rod position indicators is required to determine control rod positions and thereby ensure compliance with the control rod alignment and insertion limits.

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FARLEY-UNIT 1 B 3/4 1-3 J. .ENT NO. 123 CORRECTED BY NRC LETTER L..czD JLfE 16, 19971 I

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,' REACTIVITY CONTROL SYSTEMS RASES BORATION SYSTEMS (Continuedi with the RCS temperature below 200*F, one injection system is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity changes in the event the single injection system becomes inoperable.

The limitation for a maximum of one centrifugal charging pump to be OPERABLE and the Surveillance Requirement to verify all charging pumps except the required OPERABLE pump to be inoperable below 180*F provides assurance that a mass addition pressure transient can be relieved by the operation of a single RHR relief valve.

The boron capability required below 200*F is sufficient to provide a SHUTDOWN MARGIN as specified in the COLR after xenon decay and cooldown from 200*F to 140*F. This condition requires either 2,000 gallons of 7000 ppm borated water from the boric acid storage tanks or 7,750 gallons of 2300 ppm borated water from the refueling water storage tank.

The contained water volume limits include allowance for water not available because of discharge line location and other physical characteristics.

The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 7.5 and 10.5 for the solution recirculated l within containment after a LOCA. This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on ciechar.ical systems and components.

The OPERABILITY of one boron injection system uuring REFUELING ensures that this system is available for reactivity control while in MODE 6.

3/4.1.3 MOVABLE CONTROL ASSEMBLIES

' The specifications of this section ensure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is maintained, and (3) limit the potential effects of rod misalignment on associated accident analyses. OPERABILITY of.the control rod position indicators is required to determine control rod positions and thereby ensure compliance with the control rod alignment and insertion limits.

FARLEY-UNIT 2 8 3/4 1-3 AMENDMENT NO. 118 CORRECTED BY NRC LETTER DATEDJLNE 16,1997l

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