ML031200122

Changes to TS Associated with Nuclear Instrumentation

ML031200122
Person / Time
Site:	Seabrook
Issue date:	04/21/2003
From:	Pierre G Florida Power & Light Energy Seabrook
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NYN-02095, NYN-03032
Download: ML031200122 (8)

Text

0 FPL Energy FPL Energy Seabrook Station Seabrook Station P.O. Box 300 Seabrook, NH 03874 (603) 773-7000 April 21, 2003 Docket No. 50-443 NYN-03032 U.S. Nuclear Regulatory Commission Re: NYN-02095 ATTN: Document Control Desk Washington, D.C. 20555-0001 Seabrook Station Revision to License Amendment Request 02-03, "Changes to Technical Specifications Associated with Nuclear Instrumentation" FPL Energy Seabrook, LLC (FPLE Seabrook) has enclosed herein a revision to License Amendment Request (LAR) 02-03, NYN-02095, dated October 11, 2002.

This revision withdraws the LAR 02-03 proposed change to Technical Specification (TS) Table 4.3-1 to extend the TRIP ACTUATING DEVICE OPERATIONAL TEST surveillance interval for Functional Units 16a, Turbine Trip on Low Fluid Oil Pressure; and Functional Unit 16b, Turbine Trip on Turbine Stop Valve Closure, from 31 days to 92 days. The surveillance interval for Functional Units 16a and 16b will remain as currently licensed, i.e., 31 days. TS Table 4.3-1 and its associated Table Notations have been revised accordingly to reflect the 31 day interval. The revised markup and retype pages are enclosed and supercede those submitted in LAR 02-03.

This revision to LAR 02-03 does not make any additional changes to LAR 02-03 or its conclusion. That is, the proposed changes do not involve a significant hazards consideration pursuant to the requirements of 10 CFR 50.92 and the proposed changes continue to meet the criteria of 10CFR 51.22(c)(9) for a categorical exclusion from the requirements for an Environmental Impact Statement. Therefore, this revision to LAR 02-03 will neither adversely affect nor endanger the health and safety of the general public.

Should you have any questions regarding this letter, please contact Mr. James M. Peschel, Regulatory Programs Manager, at (603) 773-7194.

Very truly yours, FPL Energy Seabrook, LLC.

Gene F. St. Pierre Station Director Aool

U.S. Nuclear Regulatory Commission NYN-03032fPage 2 cc:

H. J. Miller, NRC Regional Administrator V. Nerses, NRC Project Manager, Project Directorate 1-2 G. Dentel, NRC Senior Resident Inspector Mr. Donald Bliss, Director New Hampshire Office of Emergency Management State Office Park South 107 Pleasant Street Concord, NH 03301

0FPL Energy Seabrook Station SEABROOK STATION UNIT I FPL Energy Seabrook, LLC submits this revision to License Amendment Request 02-03 pursuant to 10CFR50.90. The following information is enclosed in support of this revised License Amendment Request:

• Markup and Retype of the Proposed Change I, Gene F. St. Pierre, Station Director of FPL Energy Seabrook, LLC hereby affirm that the information and statements contained within this License Amendment Request are based on facts and circumstances which are true and accurate to the best of my knowledge and belief.

Av-A Gene F. St. Pierre Station Director Sworn and Subscribed before me this cS 1 -

day of April, 2003 Notary Public

MARKUP AND RETYPE PAGES The attached markup and retype pages reflect the currently issued revision of the Technical Specifications listed below.

Pending Technical Specifications or Technical Specification changes issued subsequent to this submittal are not reflected in the enclosed markup and retype pages. The enclosed retype should be checked for continuity with Technical Specifications prior to issuance.

The following Technical Specifications and Bases are included in the attached markups:

Technical Specification Title Page(s)

Table 4.3-1 Reactor Trip System Instrumentation Surveillance Requirements 3/4 3-10 3/4 3-12 Table 4.3-1 Table Notations Reactor Trip System Instrumentation Surveillance Requirements

TABLE 4.3-1 (Continuedl I INSTRUMENTATION SURELLAMCE REACTOR TRIP SYSTEM CHAN FUNCIONAL CIT McHE

13. Steam Generator Water Level-- S Low-Low

14. Undervoltage - Reactor Coolant N.A.

Pumps

15. Underfrequency - Reactor N.A.

Coolant Pumps

16. Turbine Trip

a. Low Fluid Oil Pressure N.A.

b. Turbine Stop Valve N.A.

17. Safety Injection Input from N.A.

ESF

18. Reactor Trip System Interlocks

a. Intermediate Range Neutron Flux, P-6 N.A.

b. Low Power Reactor Trips Block, P-7 N.A.

c. Power Range Neutron Flux, P-8 N.A.

d. Power Range Neutron Flux, P-9 N.A.

NEL CHANNEL CALIBRATI R

R R

R R

N.A.

R(4)

R(4)

R(4)

R(4)

ANALOG CHANNEL OPERATIONAL TESI Q

RE0UIREHEM TRIP ACTUATING DEVICE OPERATIONAL TENT N.A.

MNODES FOR WHICH ACTUATION SURVEILLANCE LOGIC TEST LIS REQUIRED N.A.

I, 2 N.A.

N.A.

N.A.

N.A.

N.A.

R R

R R

Q q

S/U(f.

10)

S/Ul, 10)

R N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

1 1

I I

1, 2 Il N.A.

N.A.

N.A.

N.A.

1 I

1

TABLE 4.3-1 (Continued)

TABLE NOTATIONS

• Only if the Reactor Trip System breakers happen to be closed and the Control Rod Drive System is capable of rod withdrawal.

• • Below P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

• • • Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

(1)

If not performed in-previous,3 days.

I (2)

Comparison of calorimetric to excore power indication above 15% of RATED THERMAL POWER.

Adjust excore channel gains consistent with calorimetric power if absolute difference is greater than 2%. The provisions of Specification 4.0.4 are not applicable to entry into MODE 2 or 1.

(3) Single point comparison of incore to excore AXIAL FLUX DIFFERENCE above 50% of RATED THERMAL POWER.

Recalibrate if.the absolute difference is greater than or equal to 3%. The provisions of Specification 4.0.4 are not applicable for entry *into MODE 2. or 1. For.the purposes of this surveillance requirement, monthly shall mean at least once per 31 EFPD.

(4)

Neutron detectors may be excluded from CHANNEL CALIBRATION.

(5) Initial plateau curves shall be measured for each detector.. Subsequent

• plateau curves shall be obtained, evaluated and compared to the initial curves.

For the Intermediate Range and Power Range Neutron Flux channels the provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(6) Incore - Excore Calibration, above 75% of RATED THERMAL POWER. The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1. For the purposes of this surveillance requirement, quarterly shall mean at least once per 92 EFPD.

(7) Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(8) oF tjor ee^FWyLIed lx) p(aSQaFtD 31 cafQ.

(9)

Surveillance in MODES 3*, 4*, and.5* shall also include verification that permissives P-6 and P-4O are in their required state for existing plant conditions by observation of the permissive annunciator window.

(10) Setpoint verification is not applicable.

(11) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.

SEABROOK - UNIT 1 3/4 3-12 Amendment No.2

TABLE 4.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS ANALOG CHANNEL OPERATIONAL TEST TRIP ACTUATING DEVICE OPERATIONAL TEST MODES FOR WHICH SURVEILLANCE IS REQUIRED CHANNEL FUNCTIONAL UNIT CHECK CHANNEL CALIBRATION ACTUATION LOGIC TEST

13.

Steam Generator Water Level-Low-Low

14.

Undervoltage - Reactor Coolant Pumps

15.

Underfrequency - Reactor Coolant Pumps

16.

Turbine Trip

a. Low Fluid Oil Pressure

b. Turbine Stop Valve

17.

Safety Injection Input from ESF

18.

Reactor Trip System Interlocks

a. Intermediate Range Neutron Flux, P-6

b. Low Power Reactor Trips Block, P-7

c. Power Range Neutron Flux, P-8

d. Power Range Neutron Flux, P-9 S

R Q

N.A.

N.A.

N.A.

N.A.

R N.A.

Q Q

N.A.

N.A.

1,2 I

1 R

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

R R

N.A.

R(4)

R(4)

R(4)

R(4)

N.A.

N.A.

N.A.

R R

R R

S/U(8, 10)

S/U(8, 10)

R N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

N.A.

I 1, 2 N.A.

N.A.

N.A.

N.A.

1 1

1 SEABROOK - UNIT 1 3/4 3-10 Amendment No. 36,

TABLE 4.3-1 (Continued)

TABLE NOTATIONS

• Only if the Reactor Trip System breakers happen to be closed and the Control Rod Drive System is capable of rod withdrawal.

• • Below P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

• • • Below P-1 0 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

(1)

If not performed in previous 92 days.

(2)

Comparison of calorimetric to excore power indication above 15% of RATED THERMAL POWER. Adjust excore channel gains consistent with calorimetric power if absolute difference is greater than 2%. The provisions of Specification 4.0.4 are not applicable to entry into MODE 2 or 1.

(3)

Single point comparison of incore to excore AXIAL FLUX DIFFERENCE above 50%

of RATED THERMAL POWER. Recalibrate if the absolute difference is greater than or equal to 3%. The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1. For the purposes of this surveillance requirement, monthly shall mean at least once per 31 EFPD.

(4)

Neutron detectors may be excluded from CHANNEL CALIBRATION.

(5)

Initial plateau curves shall be measured for each detector. Subsequent plateau curves shall be obtained, evaluated and compared to the initial curves. For the Intermediate Range and Power Range Neutron Flux channels the provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(6)

Incore - Excore Calibration, above 75% of RATED THERMAL POWER. The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1. For the purposes of this surveillance requirement, quarterly shall mean at least once per 92 EFPD.

(7)

Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(8)

If not performed in previous 31 days.

(9)

Surveillance in MODES 3*, 4*, and 5* shall also include verification that permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window.

(10)

Setpoint verification is not applicable.

(11)

The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.

SEABROOK - UNIT 1 3/4 3-12 Amendment No. 33,