ML15218A169

Amend 230 to License DPR-55,extending on one-time Basis, During Operating Cycle 17,certain Specified TS Surveillances Required to Be Performed at Frequency of 18 Months from Max Allowed Frequency of 22 months,15 Days,To Max of 24 Months

ML15218A169
Person / Time
Site:	Oconee
Issue date:	08/28/1998
From:	Berkow H NRC (Affiliation Not Assigned)
To:
Shared Package
ML15218A170	List: ML15218A169 ML15218A171
References
NUDOCS 9809030268
Download: ML15218A169 (8)

Text

pA R 1 0UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-4001 DUKE ENERGY CORPORATION DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 230 License No. DPR-55 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment to the Oconee Nuclear Station, Unit 3 (the facility)

Facility Operating License No. DPR-55 filed by the Duke Energy Corporation (the licensee) dated July 16, 1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

9809030268 980828 r

PDR ADOCK 05000287 P

PDR

-2

2.

Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 3.B of Facility Operating License No. DPR-55 is hereby amended to read as.

follows:

B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 230, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION erbert N. Berkow, irector Project Directorate 11-2 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes Date of Issuance:

August 28, 1998

ATTACHMENT TO LICENSE AMENDMENT NO. 230 FACILITY OPERATING LICENSE NO. DPR-55 DOCKET NO. 50-287 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.

Remove Insert 4.1-3 4.1-3 4.1-3a 4.1-4 4.1-4 4.5-2 4.5-2 4.20-5 4.20-5

Table 4. 1-1 INSTRUMENT SURVEILLANCE REQUIREMENTS Channel Description Check Test Calibrate Remarks

1.

Protective Channel NA MO NA Coincidence Logic in the Reactor Trip Modules

2.

Control Rod Drive NA MO(l)

NA (1)

This test shall independently Trip Breaker, SCR confirm the operability of the Control Relays E and F shunt trip device and the undervoltage device..

3.

Power Range Amplifier ES(l)

NA (1)

(1)

Heat balance check each shift.

Heat balance calibration whenever indicated core thermal power exceeds neutron power by more than 2 percent.

4.

Power Range ES 45 Days MO(1)(2)

(1)

Using incore instrumentation.

STB (2)

Axial offset upper and lower chambers after each startup if not done previous week.

5.

Wide Range ES(l)

PS NA (1)

When in service.

6.

Source Range ES(1)

PS NA (1)

When in service.

7.

Reactor Coolant ES 45 Days 18 months Temperature STB

8.

High Reactor Coolant ES 45 Days 18 months (1)

(1) A one-time extension of the test frequency to a Pressure STB maximum of 24 months is allowed for Oconee Unit 3 during operating cycle 17.

Oconee 1, 2, and 3 4.1-3 Amendment No. 230 (Unit3)

Table 4.1-1 (CONTINUED)

Channel Description Check Test Calibrate Remarks

9.

Low Reactor Coolant ES 45 Days 18 months(1)

(1) A one-time extension of the test frequency to a Pressure STB maximum of 24 months is allowed for Oconee Unit 3 during operating cycle 17.

Oconee 1, 2, and 3 4.1-3a Amendment No. 230 (Unit 3)

Table 4.1-1 (CONTINUED)

Channel Description Check Test Calibrate Remarks

10.

Flux-Reactor Coolant ES 45 Days 18 months (1)

(1) A one-time extension of the test frequency to a Flow Comparator STB maximum of 24 months is allowed for Oconee Unit 3 during operating cycle 17.

11.

Reactor Coolant Pressure ES 45 Days 18 months (1)

(1) A one-time extension of the test frequency to a Temperature Comparator STB maximum of 24 months is allowed for Oconee Unit 3 during operating cycle 17.

12.

Pump-Flux Comparator ES 45 Days 18 months STB

13.

High Reactor Building DA 45 Days 18 months Pressure STB

14.

High Pressure Injection &

NA MO NA Includes Reactor Building Reactor Building Isolation Isolation of non-essential Logic (Non-essential systems) systems

15.

High Pressure Injection Analog Channels:

a.

Reactor Coolant Pressure ES MO 18 months

b.

Reactor Building Pressure (4 psig)

ES MO 18 months

16.

Low Pressure Injection NA MO NA Logic Oconee 1, 2, and 3 4.1-4 Amendment No. 2 3 0 (Unit3)

0 4.5.1.1.3 Core Flooding System

a.

Every 18 months, a system test shall be conducted to demonstrate proper operation of the system.

During pressurization of the Reactor Coolant System, verification shall be made that the check and isolation valves in the core flooding tank discharge lines operate properly.

b.

The test will be considered satisfactory if control board indication of core flood tank level verifies that all valves have opened.

4.5.1.2 Component Tests 4.5.1.2.1 Valves - Power Operated

a.

Valves LP-17, -18, shall only be tested every cold shutdown unless previously tested during the current quarter.

b.

Every 18 months, the following LPI system valves shall be cycled manually to verify the manual operability of these power operated valves:

(1) LPI pump discharge (ES) LP-17,-18 b (2) LPI discharge throttling LP-12,-14 (3) LPI discharge header crossover LP-9,-10 (4) LPI discharge to HPI/RBS LP-15,-16 4.5.1.2.2 Check Valves Periodic individual leakage testing a of valves CF-12, CF-14, LP-47 and LP-48 shall be accomplished prior to power operation after every time the plant is placed in the cold shutdown condition for refueling, after each time the plant is placed in a cold shutdown condition for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if testing has not been accomplished in the preceding 9 months, and prior to returning the valve to service after maintenance, repair or replacement work is performed. Whenever integrity of these valves cannot be demonstrated, the integrity of the remaining valve in each high pressure line having a leaking valve shall be determined and recorded daily. In addition, the position of the other closed valve located in the high pressure piping shall be recorded daily. For the allowable leakage rates and limiting conditions for operation, see Technical Specification 3.1.6.10.

Bases The Emergency Core Cooling Systems are the principle reactor safety features in the event of loss of coolant accident. The removal of heat from the core provided by these systems is designed to limit core damage.

The High Pressure Injection System under normal operating conditions has one pump operating. The HPI system test required by Specification 4.5.1.1.1 verifies that the HPI system responds as required to actuation of ES channels I and 2.

(a)

To satisfy ALARA requirements, leakage may be measured indirectly (as from the performance of pressure indicators) if accomplished in accordance with approved procedures and supported by computations showing that the method is capable of demonstrating valve compliance with the leakage criteria.

(b)

A one-time extension of the LPI pump discharge valves LP-17 and LP-18 manual cycle test frequency is allowed to a maximum of 24 months for Oconee Unit 3 during operating cycle 17.

Oconee 1, 2, and 3 4.5-2 Amendment No. 230 (Unit 3)

'ABLE 4.20-1 SSF INSTRUMENTATION SURVEILLANCE REQUIREMENTS Check Calibrate Remarks

1.

RCS Pressure (3)

WE 18 months(4)

Loop A, B

2.

SSF RC Makeup Pump (3)

Suction Pressure QU(1) 18 months Discharge Pressure QU(1) 18 months Suction Temperature QU(1) 18 months Discharge Flow QU(l) 18 months(4)

3.

RC System Temperature (3)

NA(2) 18 months Loop A, B Hot, Cold

4.

Pressurizer Water Level (3)

WE 18 months(4)

5.

SSF Auxiliary Service Water Pump Suction Pressure QU(1)

AN Discharge Pressure QU(1)

AN Unit 1 Discharge Pressure NA AN Unit 2 Discharge Pressure NA AN Unit 3 Discharge Pressure NA AN Discharge Test Flow QU(1)

AN Suction Temperature QU(1)

AN

6.

Steam Generator Levels (3)

WE 18 months A,B

7.

Underground Fuel Oil Storage Tank NA AN Inventory

8.

D/G Service Water Pump Discharge Flow QU(1)

AN Discharge Pressure QU(1)

AN

9.

D/G Air Start System WE AN Pressure (1)

Check when pump operated/tested per IST.

(2)

This instrumentation is normally aligned through a transfer/isolation device to each Unit Control Room and is thus checked in accordance with Specification 4.1, Table 4.1-1, Item 7. Every 18 months, the instrument string to the SSF Control Room will be checked and calibrated.

(3)

Units 1, 2, 3.

(4)

A one-time extension of the test frequency to a maximum of 24 months is allowed for Oconee Unit 3 during operating cycle 17.

Oconee 1, 2, and 3 4.20-5 Amendment No. 230(Unit 3)