ML13309A266

Amend 146 to License DPR-13,revising TS Concerning ECCS to Incorporate Specific Requirements for Operation of Recirculation Sys

ML13309A266
Person / Time
Site:	San Onofre
Issue date:	06/24/1992
From:	Quay T Office of Nuclear Reactor Regulation
To:
Shared Package
ML13309A265	List: ML13309A264 ML13309A266 ML13309A268
References
DPR-13-A-146 NUDOCS 9207020243
Download: ML13309A266 (8)

Text

00 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY DOCKET NO. 50-206 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.146 License No. DPR-13

1.

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

A.

The application for amendment by Southern California Edison Company (the licensee) and the San Diego Gas and Electric Company dated August 31, 1990, and supplemented November 1, 1990, September 9, 1991, and June 5, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as amended, 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; 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.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. DPR-13 is hereby amended to read as follows:

9207020243 920624 PDR ADOCK 05000206 P

PDR

-2 (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.146, are hereby incorporated in the license.

Southern California Edison Company shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and must be fully implemented no later than 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Theodore R. Quay, Director Project Directorate V Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: June 24, 1992

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 146 TO FACILITY OPERATING LICENSE NO. DPR-13 DOCKET NO. 50-206 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the areas of change.

REMOVE INSERT 3.3-1 3.3-1 3.3-2 3.3-2 3.3-3 3.3-3 3.3-4 3.3-4 3.3-5 3.3-5

3.3 SAFETY INJECTION, RECIRCULATION, and CONTAINMENT SPRAY SYSTEMS 3.3.1 OPERATING STATUS APPLICABILITY:

Applies to the operating status of the Safety Injection, Recirculation, and Containment Spray Systems.

OBJECTIVE:

To define those conditions and components that are necessary to ensure availability of the Safety Injection, Recirculation and Containment Spray Systems.

SPECIFICATION:

A. In Modes 1, 2, and in Mode 3 when the RCS pressure is greater than or equal to 600 psig, two trains of the Safety Injection, Hot Leg Recirculation, Cold Leg Recirculation, and Secondary Recirculation Systems shall be OPERABLE.

Safety Injection and Recirculation Systems are comprised of:

1. Three RWST ESF Switchover automatic trip channels per train, with the setpoint less than or equal to 20% and greater than or equal to 18% of RWST level.

2.

Two safety injection pumps.

3. Two feed water pumps.

4. Two recirculation pumps.

5. The recirculation heat exchanger.

6. Two charging pumps.

7. Two component cooling water pumps.

8. Two saltwater cooling pumps.

9. A minimum of 5400 pounds of anhydrous trisodium phosphate stored in the containment sump in racks provided.

10. Flow paths, valves, and interlocks associated with each train or common to both trains of the systems.

B. In Mode 3 when the RCS pressure is less than 600 psig and in Mode 4, one train of the Hot Leg Recirculation and Cold Leg Recirculation Systems shall be OPERABLE.

SAN ONOFRE - UNIT 1 3.3-1 AMENDMENT NO: 7, 37, $6, 124, 130. 146

C. In Modes 1, 2, 3, and 4, two trains of the Containment Spray System and associated portions of the Recirculation System shall be OPERABLE.

Containment Spray System is comprised of:

1. Two refueling water pumps.

2.

Two hydrazine additive pumps.

3. Flow paths, valves, and interlocks associated with each train or common to both trains of the system.

D. Effective leakage from the Recirculation loop outside the containment shall be less than 625 cc/hr as calculated from the following formula.

Effective Leakage = (a, x Ll) + (a2 x L2) + (a3 x L3)

where, L, = pump and valve leakage which drains to auxiliary building sump L2 = valve leakage in auxiliary building or doghouse L2 = valve leakage outside a, = iodine release factor for leakage in auxiliary building sump a2 = iodine release factor for leakage in auxiliary building or doghouse as = iodine release factor for leakage outside the auxiliary building or doghouse ACTIONS:

A. With one train of the Safety Injection System, Hot Leg Recirculation System, Cold Leg Recirculation System, Secondary Recirculation System, or necessary support systems inoperable when RCS pressure is greater than or equal to 600 psig, restore the inoperable train for each system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce RCS pressure to less than 600 psig within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SAN ONOFRE - UNIT 1 3.3-2 AMENDMENT NO:

25, 1Z0, 146

B. With both trains of the Hot Leg Recirculation or Cold Leg Recirculation Systems, or necessary support systems inoperable when RCS pressure is less than 600 psig, restore at least one train to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.

C. 1. With one train of Containment Spray System, associated portions of the Recirculation System, or necessary support systems inoperable, restore the inoperable train for each system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

2.

With one containment spray flow limiter valve inoperable, close the valve if either recirculation pump is inoperable. Restore the inoperable valve to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

D. If effective leakage from the recirculating loop outside the containment exceeds 625 cc/hr, make necessary repairs to limit leakage to 625 cc/hr within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

BASIS:

The requirements of this specification assure that before the reactor can be made critical, or before the reactor coolant system heatup is initiated, adequate engineered safeguards are OPERABLE.

Amendment Application No. 188 incorporated new requirements to address the operability of Emergency Core Cooling System (ECCS) subsystems, trains, and action requirements for inoperable trains(s), consistent with the guidance provided in the Standard Technical Specifications. When the RCS pressure is greater than or equal to 600 psig in Modes 1, 2 and 3, the ECCS, consisting of the Safety Injection, Normal and Alternative Hot Leg Recirculation, Cold Leg Recirculation, Secondary Recirculation and Containment Spray Systems, is required to be OPERABLE. Operability of redundant trains and components provides protection for single active failures. For example, the RWST ESF Switchover train is inoperable when one or more of the RWST level channels for that train is inoperable.

The 72-hour period provided for performing surveillance testing, preventive and corrective maintenance, is applied to all components for one train. In addition to the ECCS trains the action statements also address, "necessary support systems."

Any support system, such as back-up Nitrogen or Component Cooling Water, is required for the ECCS when necessary to support the safety function. This is consistent with the definition of OPERABILITY in Section 1.

SAN ONOFRE - UNIT 1 3.3-3 25, 38, E0,

124, 10, 142 146

When RCS pressure is below 600 psig in Modes 3 and 4, only a single train of the Hot Leg Recirculation and Cold Leg Recirculation Systems and the common ECCS flow paths are required to be operable due to the stable reactivity condition of the reactor and limited core cooling requirements. Note that the Containment Spray System is required to have both trains OPERABLE in Modes 1, 2, 3 and 4, consistent with the Standard Technical Specifications. The Hot Leg Recirculation and Cold Leg Recirculation Systems include components that support containment spray (the recirculation pumps, heat exchanger, valves and flow paths). Note that both trains of those portions of the recirculation system which support containment spray are required through Mode 4. Refueling Water Storage Tank and boron concentration requirements are in Specification 3.3.3.

Secondary recirculation is a means of providing cooling after a Main Steam Line Break which disables the RHR system inside the containment. The flow path takes water from the sump and returns it to the RWST using recirculation and refueling water pumps. The feedwater and safety injection pumps are aligned to supply the secondary side of the steam generators using the feedwater bypass valves.

The containment spray system consists of two redundant trains, which satisfy the single failure criterion. At least one containment spray flow limiter valve must be open during the initial containment spray mode to pass the design flow rate of the Containment Spray System. Since the flow limiting valves require non-safety related instrument air to open, the flow limiting valves are maintained in the open position to assure the valves will be in the correct position for containment spray. For operation during the recirculation phase both valves are closed. Instrument air is not required to close the valves. One of the two valves is permitted to be inoperable for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> but must be placed in the closed position if one of the recirculation pumps is inoperable.

When both recirculating water pumps are operable, a spray flow limiter valve can be inoperable in the open position for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Both recirculation pumps are needed when one valve is inoperable and open to assure adequate NPSH is available to the recirculation pumps under the higher spray flow conditions.

Below an RCS pressure of 600 psig, the safety injection system may be isolated in accordance with Specification 3.3.2.

Additional charging pump technical specification requirements are included in Specification No. 3.2, "Chemical and Volume Control System."

When the reactor is in Modes 1-4, preventive or corrective maintenance or surveillance testing is allowed in accordance with the Action Statement time limits. The specified maintenance times are a maximum, and maintenance work will proceed with diligence to return the equipment to an OPERABLE SAN ONOFRE - UNIT 1 3.3-4 AMENDMENT NO: i5, 17, 10, ZZ0, 146

condition as promptly as possible. OPERABILITY of the specified components shall be based on the verification that the appropriate surveillance tests have been performed.

In the unlikely event that the need for safety injection should occur:

-- functioning of one train will protect the core.

Containment sprays alone, however, will maintain containment pressure under design pressure.

-- functioning of one of the two hydrazine additive pumps and associated discharge valve will effect introduction of hydrazine into containment spray water. This provides for absorption of airborne fission products and reduction of the thyroid doses associated with the maximum hypothetical accident to within 10 CFR 100 limits.

-- dissolution of 5400 pounds of anhydrous trisodium phosphate stored in the sump will ensure that the pH of the water in the sump will be greater than 7 within four (4) hours, so as to prevent chloride stress corrosion cracking of systems and components exposed to the circulating sump water.

The switchover from injection to recirculation modes is a two part process, which consists of the automatic termination of the flow from SI/FW pumps including automatic pump trip and automatic closures of MOV's 850 A, B and C followed by manual realignment to recirculation from the containment sump. The automatic trip setpoint is bounded by the minimum water level in the sump to support recirculation for long term post-LOCA cooling and the minimum RWST level to support charging and containment spray during the manual realignment. The setpoint analysis conservatively determined the automatic trip setpoint to be 20% of the RWST level.

The automatic trip setpoint is the result of the combination of the worst single active failure considering SIS and SISLOP conditions.

The limit of 625 cc/hr for the recirculation loop leakage ensures that the combined 0-2 hr EAB thyroid dose due to recirculating loop leakage and containment leakage will not exceed the limits of 10 CFR 100. The formula for determining the leakage incorporates consideration of the significance of leakage in different plant areas. The iodine release factor adjusts actual pump or valve leakage to account for the fraction of the iodine in the leakage which would actually be released to the atmosphere. The iodine release factors in the auxiliary building sump, the auxiliary building or doghouse, and outside are 0.05, 0.5, and 1.0, respectively.

REFERENCES:

(1) Updated Safety Analysis Report, Chapters 6 and 15.

(2) Event Specific Single Failure Response Evaluation, SONGS 1, M-39419, Rev.3.

(3) Single Failure Analysis, SONGS 1, M-41383, Rev. 1.

SAN ONOFRE - UNIT 1 3.3-5 AMENDMENT NO: i5, 1Z0, 146