ML20149M293

Forwards Proposed Rev to TS Bases Section 3/4.2.5 for Plant

ML20149M293
Person / Time
Site:	Farley
Issue date:	12/11/1996
From:	Jacob Zimmerman NRC (Affiliation Not Assigned)
To:	Dennis Morey SOUTHERN NUCLEAR OPERATING CO.
References
TAC-M97276, TAC-M97277, NUDOCS 9612160017
Download: ML20149M293 (5)

Text

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December 11, 1996 Mr. D. N. Morey Vice PresidInt - Farley Project.

,f South 2rn Nuclear Operating,

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4 Company, Inc.-

Post Offics Box ~1295 a

Birmingh'am,iAlabama-35201-1295

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SUBJECT:

A.

PROPOSED REVISION.TO TECHNICAL SPECIFICATION BASES FOR JOSEPH M.

FARLEY,NUCLEA PL.NT7 UNITS 1:AND 2 (TAC NOS. M97276 AND M97277)

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Dear Mr. Morey:

Byletter"datedNovImber 18, 1996', Sou,hern Nuclear Operating Company (SNC) provided the Nuclear Regulatory Commission's (NRC) staff revised pages for the Technical Specification (TS) Bases Section 3/4.2.5 for the Joseph M. Farley i

Nuclear Plant, Units 1 and 2.

The revision to the Bases section was the result of a safety evaluation performed by SNC that allows the use of either the precision calorimetric-based flow measurement method or an alternate method using the cold leg elbow taps to satisfy the requirements of the 18-month RCS total flow surveillance.

As you are aware, the TS Bases are not part of the TS as defined by 10 CFR

-50.36.

As such, changes to the TS Bases may be made in accordance with the provisions of 10 CFR 50.59. Should the proposed change involve an unreviewed safety question pursuant to 10 CFR 50.59(a)(2), or involve a change in the interpretation of implementation of the TS (i.e., constitute a TS change),

then the proposed change is to be provided to the staff pursuant to the provisions of 10 CFR 50.59(c) and 10 CFR 50.90 for prior NRC review and approval.

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 timely fashion.

Enclosed is a copy of the Farley revised TS Bases pages B 3/4 2-5 for Units 1 and 2 that have been dated to correspond to the issue date of this letter.

Sincerely, j

Original signed by:

h Jacob I. Zimmerman, Project Manager 2

Project Directorate II-2 e

Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364

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Units 1 and 2 Revised PUBLIC ACRS

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2066H001

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December 11, 1996 Mr. D. N. Morey Vice President - Farley Project Southern Nuclear Operating Company, Inc.

Post Office Box 1295 Birmingham, Alabama 35201-1295

SUBJECT:

PROPOSED REVISION TO TECHNICAL SPECIFICATION BASES FOR JOSEPH M.

FARLEY NUCLEAR PLANT, UNITS 1 AND 2 (TAC NOS. M97276 AND M97277)

Dear Mr. Morey:

By letter dated November 18, 1996, Southern Nuclear Operating Company (SNC) provided the Nuclear Regulatory Commission's (NRC) staff revised pages for the Technical Specification (TS) Bases Section 3/4.2.5 for the Joseph M. Farley Nuclear Plant, Units 1 and 2.

The revision to the Bases section was the result of a safety evaluation performed by SNC that allows the use of either the precision calorimetric-based flow measurement method or an alternate method using the cold leg elbow taps to satisfy the requirements of the 18-month RCS total flow surveillance.

As you are aware, the TS Bases are not part of the TS as defined by 10 CFR 50.36. As such, changes to the TS Bases may be made in accordance with the provisions of 10 CFR 50.59.

Should the proposed change involve an unreviewed safety question pursuant to 10 CFR 50.59(a)(2), or involve a change in the interpretation of implementation of the TS (i.e., constitute a TS change),

then the proposed change is to be provided to the staff pursuant to the provisions of 10 CFR 50.59(c) and 10 CFR 50.90 for prior NRC review and approval.

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 timely fashion.

Enclosed is a copy of the Farley revised TS Bases pages B 3/4 2-5 for Units 1 and 2 that have been dated to correspond to the issue date of this letter.

Sincerely, Y

J cob I.

immerman, Project Manager Project Directorate 11-2 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 cc w/encls: See next page

k Mr. D. N. Morey Joseph M. Farley Nuclear Plant Southern Nuclear Operating Company, Inc.

cc:

Mr. R. D. Hill, Jr.

General Manager -

4 Southern Nuclear Operating Company Post Office Box 470 a

I-Ashford, Alabama 36312

)

.Mr. Mark Aj1 uni, Licensing Manager l

Southern Nuclear Operating Company Post Office Box 1295 j

Birmingham, Alabama. 35201-1295 j

Mr. M. Stanford Blanton Balch and Bingham Law Firm a

Post Office Box 306 i

1710 Sfxth Avenue North Birmingham, Alabama 35201 Mr. J. D. Woodard Executive Vice President Southern Nuclear Operating Company Post Office Box 1295 Bireingham, Alabama 35201 State Health Officer i

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 101 Marietta Street, NW., Suite 2900 Atlanta, Georgia 30323 Resident Inspector U.S. Nuclear Regulatory Commission 7388 N. State Highway 95 Columbia, Alabama 36319

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W PO4ER DISTRIBUTION LIMITS BASES 1

3/4.2.4 OUADRANT POWER TILT RATIO The quadrant power tilt ratio limit assures that the radial power distribution satisfies the design values used in the power capability analysis. Radial power distribution measurements are made during startup testing and periodically during power operation.

The limit of 1.02, at which corrective action is required, provides DNB and linear heat generation rate protection with x-y plane power tilts.

The two hour time allowance for operation with a tilt condition greater than 1.02 but less than 1.09 is provided to allow identification and correction of a dropped or misaligned control rod.

In the event such action does not correct i

the tilt, the margin for uncertainty on Fg is reinstated by reducing the maximum allowed power by 3 percent for each percent of tilt in excess of 1.0.

For purposes of monitoring QUADRANT POWER TILT RATIO when one excore detector is inoperable, the movable incore detectors are used to confirm that the i

normalized symmetric power distribution is consistent with the QUADRANT POWER TILT RATIO.

The incore detector monitoring is done with a full incore flux map or two sets of four symmetric thimbles. The two sets of four symmetric thimbles is a unique set of eight detector locations. These locations are C-8, 1

E-5, E-11, H-3, H-13, L-5, L-11, and N-8.

3/4.2.5 DNB PARAMETERS The limits on the DNB related parameters assure that each of the parameters are maintained within the normal steady state envelope of operation assumed in the i

transient and accident analyses.

The limits are consistent with the initial FSAR assumptions and have been analytically demonstrated adequate to meet the DNB design criterion throughout each analyzed transient. The indicated T value of SRO.7*F is based on the average of two control board readings andy2n indication..ncertainty of 2.5'F.

The indicated pressure value of 2205 psig is based on the average of two control board readings and an indication uncertainty of 20 psi.

The indicated total RCS flow rate is based on two elbow tap measurements from each loop and an uncertainty c ? 2.4% flow (0.1% flow is included for feedwater venturi fouling).

The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> surveillance of T and pressurizer pressure through the control ay board readings are sufficient t$ ensure that the parameters are restored within their limits following load changes and other expected transient operation.

The 18 month surveillance of the total RCS flow rate may be performed by one of two alternate methods. One method is a precision calorimetric performed at the beginning of each fuel cycle. The other method is based on the Ap measurements from the cold leg elbow taps, which are correlated to past precision heat balance measurements. Correlation of the flow indication channels with selected precision loop flow calorimetrics for this method is documented in WCAP-14750. Use of the elbow tap Ap measurement method removes the requirement for performance of a precision RCS flow calorimetric measurement for that cycle. The monthly surveillance of the total RCS flow rate is a reverification of the RCS flow requirement using process computer indications of loop elbow tap measurements that are correlated either to the precision RCS flow measurement or the elbow tap measurement at the beginning of the fuel cycle. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> RCS flow surveillance is a qualitative verification of significant flow degradation using the control board indicators fed,by elbow tap measurements.

Revised by NRC letter FARLEY-UNIT 1 B 3/4 2-5 dated: December 11. 1996

O i

POWER DISTRIBUTION LIMITS l

l mAsEs f

3/4.2.4 OUADRANT POWER TILT RATIO l

The quadrant power tilt ratio-limit assures that the radial power distribution satisfies the design values used in the power capability analysis. Radial power distribution measurements are made during startup testing and

)

periodically during power operation.

l The limit of 1.02, at which corrective action is required, provides DNB and linear heat generation rate protection with x-y plane power tilts.

1 The two. hour time allowance for operation with a tilt condition greater than l

1.02 but less than 1.09 is provided to allow identification and correction of a dropped or misaligned control rod.

In the event such action does not correct 1

the tilt, the margin for uncertainty on Fg is reinstated by reducing the j

maximum allowed power by 3 percent for each percent of tilt in excess of 1.0.

I For purposes of monitoring QUADRANT POWER TILT RATIO when one excore detector i

is inoperable, the movable incore detectors are used to confirm that the i

normalized symmetric power distribution is consistent with the QUADRANT POWER j

TILT RATIO. The incore detector monitoring is done with a full incore flux map or two sets of four symmetric thimbles.. The two sets of four symmetric thimbles is a unique set of eight detector locations. These locations are C-8, E-5, E-11, H-3, H-13, L-5, L-ll, and N-8.

3/4.2.5 DNB PARAMETERS The limits on the DNB related parameters assure that each of the parameters are maintained within the normal steady state envelope of operation assumed in the transient and accident analyses. The limits are consistent with the initial FSAR assumptions and have been analytically demonstrated adequate to meet the DNB design criterion throughout each analyzed transient. The indicated T value of 580.7'F is based on the average of two control board readings and 8n indication uncertainty of 2.5'F.

The indicated pressure value of 2205 psig is based on the average of two control board readings and an indication uncertainty of 20 psi. The indicated total RCS flow rate is based on two elbow tap measurements from each loop and an uncertainty of 2.4% flow (0.1% flow is included for feedwater venturi fouling).

The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> surveillance of T and pressurizer pressure through the control j

boardreadingsaresufficientt$ensurethattheparametersarerestored av i

within their limits following load changes and other expected transient operation.

The 18 month surveillance of the total RCS flow rate may be performed by one of two alternate methods. One method is a precision calorimetric performed at the

]

beginning of each fuel cycle. The other method is based on the Ap measurements from the cold leg elbow tape, which are correlated to past precision heat balance measurements. Correlation of the flow indication channels with selected precision loop flow calorimetrics for this method is documented in WCAP-14750.

Use of the i

elbow tap Ap measurement method removes the requirement for performance of a precision RCS flow calorimetric measurement for that cycle. The monthly surveillance of the total RCS flow rate is a reverification of the RCS flow requirement using process computer indications of loop elbow tap measurements that are correlated either to the precision RCS flow measurement or the elbow tap measurement at the beginning of the fuel cycle. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> RCS flow surveillance is a qualitative verification of significant flow degradation using the control board indicators fed by elbow tap measurements.

Revised by NRC letter FARLEY-UNIT 2 B 3/4 2-5 dated: December 11. 1996