ML13331A401

Proposed Tech Specs Re Containment Venting

ML13331A401
Person / Time
Site:	San Onofre
Issue date:	05/03/1990
From:	SOUTHERN CALIFORNIA EDISON CO.
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ML13331A400	List: ML13331A399 ML13331A401
References
NUDOCS 9005070328
Download: ML13331A401 (11)

Text

SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 1 TECHNICAL SPECIFICATIONS TABLE OF CONTENTS SECTION PAGE 3.4 TURBINE CYCLE.

3.4-1 3.4.1 Operating Status.

3.4-1 3.4.2 Maximum Secondary Coolant Activity.....

3.4-3 3.4.3 Auxiliary Feedwater System......

3.4-4 3.4.4 Auxiliary Feedwater Storage Tank......

..3.4-5 3.5 INSTRUMENTATION AND CONTROL..................

3.5-1 3.5.1 Reactor Trip System Instrumentation..

3.5-1 3.5.2 Control Rod Insertion Limits.....

3.5-6 3.5.3 Control and Shutdown Rod Misalignment.......

3.5-10 3.5.4 Rod Position Indicating System.......

3.5-13 3.5.5 Containment Isolation Instrumentation.......

3.5-15 3.5.6 Accident Monitoring Instrumentation........

3.5-19 3.5.7 Auxiliary Feedwater Instrumentation........

3.5-22 3.5.8 Radioactive Liquid Effluent Instrumentation...

3.5-26 3.5.9 Radioactive Gaseous Process and Effluent 3.5-29 Monitoring Instrumentation 3.5.10 Radiation Monitoring Instrumentation.......

3.5-32 3.6 CONTAINMENT SYSTEMS............

3.6-1 3.6.1 Containment Sphere..........

3.6-1 3.6.2 Containment Isolation Valves.....

3.6-3 3.6.3 Hydrogen Monitors and Hydrogen Recombiners...

3.6-6 3.6.4 Containment Air Locks.

3.6-7 3.6.5 Containment Ventilation Isolation Valves Valve Leakage.

3.6-8 3.6.6 Containment Ventilation Isolation Valves Valve Position.

3.6-9 3.7 AUXILIARY ELECTRICAL SUPPLY..............

3.7-1 3.8 FUEL LOADING AND REFUELING.

3.8-1 3.9 MODERATOR TEMPERATURE COEFFICIENT (MTC).....

3.9-1 3.10 INCORE INSTRUMENTATION.

3.10-1 3.11 CONTINUOUS POWER DISTRIBUTION MONITORING......

3.11-1 3.12 CONTROL ROOM EMERGENCY AIR TREATMENT SYSTEM.......

3.12-1 3.13 SHOCK SUPPRESSORS (SNUBBERS) OPERABILITY......

3.13-1 3.14 FIRE PROTECTION SYSTEMS OPERABILITY..........

3.14-1 3.14.1 Fire Suppression Water System......

3.14-1 3.14.2 Spray and/or Sprinkler Systems.........

...3.14-3 3.14.3 Foam Suppression System.......

3.14-7 3.14.4 Halon Systems............

3.14-9 3.14.5 Fire Hose Stations..........

3.14-11 SAN ONOFRE - UNIT 1 vi AMENDMENT NO:

90, 130, 131, 90050C)70 32E:8 9()0503 PDR ADOCK 050KO206 P

PDiC

3.6.4 CONTAINMENT AIR LOCKS APPLICABILITY: Applies to the operability and leakage limitations of the containment personnel air locks in Modes 1, 2, 3 and 4.

OBJECTIVE:

To verify leakage from the containment personnel air locks is maintained within specified values.

SPECIFICATION:

Each containment air lock shall be OPERABLE with:

A. Both doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closed, and B. Overall air lock leakage shall not exceed the maximum acceptable values specified in Specification 4.3.1.

ACTION:

C. With one containment air lock door or its associated equalizing valve inoperable:

1. Maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock the OPERABLE air lock door closed.

2. Operation may then continue until performance of the next required 6-month air lock leakage test provided that the OPERABLE air lock door is verified to be locked closed at least once per 31 days.

3. Otherwise, be in at least HOT STANDBY within the next six hours and in 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 />.

4. The provisions of Specification 3.0.4 are not applicable.

D. With the containment air lock or its associated equalizing valve inoperable, except as the result of an inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the next six hours and in 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 />.

BASIS:

The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate. Surveillance testing of the air locks provides assurance that the overall airlock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.

SAN ONOFRE - UNIT 1 3.6-7 AMENDMENT NO:

3.6.5 CONTAINMENT VENTILATION SYSTEM ISOLATION VALVES - VALVE LEAKAGE APPLICABILITY:

Applies to the leakage limitations of the containment ventilation system isolation valves in Modes 1, 2, 3, and 4.

Applicable Isolation Valves:

POV-9, Containment Purge Supply Valve POV-10, Containment Purge Exhaust Valve CV-116, Containment Sphere Equalization Valve CV-10, Containment Ventilation Valve OBJECTIVE:

To verify leakage from the applicable isolation valves is maintained within specified values.

SPECIFICATION:

The applicable valves shall be OPERABLE with a measured leakage not exceeding the limits of Surveillance Requirement 4.3.1.III.B.

ACTION:

When the measured leakage rate for any of the following isolation valves exceeds the limits of Surveillance Requirement 4.3.1.III.B, the valve(s) shall be declared inoperable. The inoperable valve(s) shall be restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or the plant shall 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 in 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 />.

BASIS:

Leakage integrity tests with a maximum allowable leakage rate for the subject isolation valves will provide early indication of resilient material and seal degradation and will allow the opportunity for repair before gross leakage failure develops.

SAN ONOFRE -

UNIT 1 3.6-8 AMENDMENT NO:

3.6.6 CONTAINMENT VENTILATION SYSTEM ISOLATION VALVES - VALVE POSITION APPLICABILITY:

Applies to the valve position (open or closed) of the containment ventilation system isolation valves in Modes 1, 2, 3, and 4. Applicable Isolation Valves:

POV-9, Containment Purge Supply Valve POV-10, Containment Purge Exhaust Valve CV-116, Containment Sphere Equalization Valve CV-10, Containment Ventilation Valve CV-40, Instrument Air Exhaust Valve OBJECTIVE:

To maintain isolation in the containment purge lines and to maintain CV-116, CV-40, and CV-10 in the isolated or closed position to the maximum extent practicable.

SPECIFICATION:

In order to achieve isolation with valves POV-9 and POV-10, the manual isolation valves CVS-301 and CVS-313 shall be locked in the closed position.

Valves CV-10 and CV-116 shall be closed to the maximum extent practicable. The valve(s) may only be opened for the following reasons:

To allow containment ventilation system operation for pressure control.

To satisfy ALARA concerns and lower airborne radiation levels upon containment entry.

For surveillance tests that require the valve(s) to be open.

The opening angle for CV-116 and CV-10 shall be limited to a approximately 50 degrees (90 degrees being full open).

Valve CV-40 shall be maintained in the isolated position except as required for surveillance testing. CV-40 is a three-way valve controlling flow of collected exhausted instrument air. This valve can direct flow to the 6-inch containment vent line or into the containment atmosphere.

CV-40 shall be maintained in the position to exhaust flow into the containment atmosphere, which is the isolated position.

ACTION:

When any of the applicable valves are not in a position allowed in the SPECIFICATION section above, the valve shall be closed or blind flanged within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or the plant shall 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 in 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 />.

SAN ONOFRE - UNIT 1 3.6-9 AMENDMENT NO:

BASIS:

Opening of the containment ventilation and sphere equalization valves, CV-10 and CV-116, is limited to periodic containment pressure reduction, air circulation for ALARA considerations upon personnel entry, and for performing valve surveillances. These limitations will maximize the amount of time that the valves are closed during power operation. In the closed position, these valves serve as a pressure barrier to provide containment isolation in the event of a steam line break or loss of coolant accident. Although both of these valves have been proven capable of closing during an accident event, by keeping them both closed to the maximum extent practicable, it is more likely that they will already be closed in the event of an accident and not have to change position.

By maintaining CV-40 in the position in which it vents exhausted instrument air into the containment atmosphere, it is maintained in its isolated position.

The containment isolation valves in (CV-116 and CV-10) are limited to a maximum opening angle of 53.5* (90* being full open) during operation. The valves have been demonstrated to be capable of closure from this opening angle under the differential pressure generated by a design basis accident. (12)

The isolation valves of the Sphere Purge Air Supply (POV-9) and Air Outlet (POV-10) lines have not been demonstrated capable of closure under the differential pressures generated by a design basis accident. For this reason, isolation in these lines shall be maintained. This shall be accomplished by locking closed the manual isolation valves CVS-301 and CVS-313. These valves shall remain locked closed during MODES 1, 2, 3, and 4 until POV-9 and POV-10 can be demonstrated capable of performing their containment isolation function under post accident conditions.

REFERENCE:

(1) SCE to NRC letter dated March 27, 1984, from M. 0. Medford to D. M. Crutchfield.

(2) NRC to SCE letter dated November 2, 1984, from J. A. Zwolinski to K. P. Baskin, Transmits NRC Safety Evaluation.

SAN ONOFRE -

UNIT 1 3.6-10 AMENDMENT NO:

4.3 CONTAINMENT SYSTEMS 4.3.1 CONTAINMENT TESTING APPLICABILITY: Applies to containment leakage.

OBJECTIVE:

To verify that leakage from the containment sphere is maintained within specified values.

SPECIFICATION:

1. Integrated Leakage Rate Tests, Type A A. Test Pressure In order to verify leakage from the containment sphere, a Type A test shall be performed. Type A tests shall consist of a peak pressure test or a reduced pressure test.

Peak pressure tests are conducted at a test pressure greater than or equal to 49.4 psig, and reduced pressure tests are conducted at a test pressure greater than or equal to 24.7 psig.

B. Acceptance Criteria For the peak pressure test program the containment sphere leakage rate measured is less than 0.090 wt%/24 hours of the initial content of the containment air at the calculated peak pressure of 49.4 psig. For the reduced pressure test program to be conducted at 24.7 psig, the measured leakage rate shall be less than 0.064 wt%/24 hours of the initial content of the containment atmosphere at the calculated peak pressure of 49.4 psig.

The accuracy of each Type A test is verified by a supplemental test which (1) confirms the accuracy of the Type A test by verifying that the difference between supplemental and Type A test data is within 25% of 0.12 wt%/24 hours for the peak pressure test or 0.085 wt%/24 hours for the reduced pressure test, and (2) requires the quantity of air bled from or injected into the containment during the supplemental test to be equivalent to at least 75 percent of the total allowable leakage rate at 49.4 psig.

SAN ONOFRE - UNIT 1 4.3-1 AMENDMENT NO:

24, 58, 75, 130,

C. Frequency A set of 3 periodic Type A tests are performed at 40 +

10 month intervals during each 10-year service period.

The third test of each set is performed when the plant is shut down for the 10-year plant inservice inspection. The permissible period for Type A testing shall be limited to periods when the plant facility is nonoperational and secured in the shutdown condition.

If any periodic Type A test fails to meet the acceptance criteria above, the test schedule applicable to subsequent Type A tests shall be submitted to the NRC for review and approval.

If two consecutive periodic Type A tests fail to meet the above acceptance criteria, a Type A test is performed at each plant shutdown for refueling or approximately every 18 months, whichever occurs first, until two consecutive Type A tests meet the acceptance criteria, after which time the normal test schedule may be resumed.

II. Containment Penetration Leakage Rate Tests (Type B)

A. Test Pressure Type B tests are conducted at a test pressure at or above 49.4 psig. Personnel airlocks are tested every six months at or above 49.4 psig. In addition, a lower pressure test at or above 3 psig is performed on the personnel airlocks as required by Section II.C.

B. Acceptance Criteria The combined leakage rate of all penetrations subject to Type B tests and all containment isolation valves subject to Type C tests is less than 0.072 wt%/24 hours of the initial content of the containment atmosphere at the calculated peak pressure of 49.4 psig. The overall air lock leakage is less than 0.012 wt%/24 hours for the 49.4 psig test and less than 0.0024 wt%/24 hours for the 3 psig test.

C. Test Schedule Type B tests, except for airlocks, are performed during every reactor shutdown for refueling, or other convenient intervals, but in no case at intervals greater than two years.

Airlock volumes between the doors are tested:

(1) at least every six months at 49.4 psig, SAN ONOFRE - UNIT 1 4.3-2 AMENDMENT NO: 5, 24, 58, 75, 87, 118, 130,

(2) within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following each closing, except when the airlock is being used for multiple entries, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, at or above 3 psig test pressure, and (3) prior to establishing CONTAINMENT INTEGRITY when maintenance has been performed on the airlock that could affect the airlock sealing capability at 49.4 psig.*

III. Containment Isolation Valve Leakage Rate Tests (Type C)

A. Test Pressure Type C tests are conducted in accordance with the criteria specified in Appendix J of 10 CFR 50.

These Type C tests are conducted at a test pressure at or above 49.4 psig.

B. Acceptance Criteria (Maximum acceptable value)

The combined leakage rate of all penetrations subject to Type B tests and all containment isolation valves subject to Type C tests is less than.072 wt%/24 hours of the initial content of the containment atmosphere at the calculated peak pressure of 49.4 psig. The measured leakage for the 24-inch containment purge supply and return isolation valves, and the 6-inch containment ventilation isolation valves is less than 0.012 wt%/24 hours per line.

C. Test Schedule Type C tests are performed during each reactor shutdown for refueling, or other convenient intervals, but in no case at intervals greater than two years.

Seal tests conducted on active containment ventilation isolation valves shall be performed every three months.

Seal tests conducted on passive containment ventilation isolation valves shall be performed every six months.

• Exemption to Appendix J of 10 CFR 50 SAN ONOFRE - UNIT 1 4.3-3 AMENDMENT NO:

24, 58, 87, 118, 130,

IV. Recirculation System A. Test Pressure Leak tests shall be performed on portions of the Safety Injection System used for recirculation at a pressure equal to or greater than the operating pressure under accident conditions. The test fluid shall be water.

B. Acceptance Criteria Visual inspection for leakage shall be made and if leakage can be detected, measurements of such leakage shall be made. The maximum effective leakage shall be maintained in accordance with Section 3.3.1.A(4) of Appendix A Technical Specifications.

C. Test Schedule Visual inspections of the recirculation loop outside containment (including the Containment Spray System))

shall be made at intervals not to exceed the normal plant refueling interval.

In addition, pumps and valves of the recirculation loop outside containment which are used during normal operation, shall be visually inspected for leakage at intervals not to exceed once every six months.

V. Test Result Report The results of Type A, B, and C leakage rate tests are submitted to the NRC in a summary technical report approximately three months after the conduct of the Type A tests. This report contains an analysis and interpretation of the Type A test results and a summary of periodic Type B and C tests performed since the last Type A test. Leakage rate test results from Type A tests that fail to meet the acceptance criteria specified in Section I.B above are reported in a separate attached summary report that includes an analysis of the test data, an instrumentation error analysis, and the structural conditions of the containment or components, if any, which contributed to failure in meeting the acceptance criteria.

Results and analysis of the supplemental verification test used to demonstrate the validity of the Type A test measurements are included.

SAN ONOFRE - UNIT 1 4.3-4 AMENDMENT NO:

24, 87, 130,

VI. Containment Modification Any major modification or replacement of a component that is part of the containment boundary is followed by Type A, B, or C tests as applicable. The results of such tests are included in the test result report described above and meet the respective acceptance criteria. Minor modifications or replacements performed directly prior to the conduct of a scheduled Type A test do not require a separate test.

Bases:

The containment system is one of the major engineered safety features and is a consequence-limiting system, it represents the final physical barrier that, in the event of a loss-of-coolant accident (LOCA), protects against the inadvertent release of fission products.

I. Leakage Rate Testing Periodic containment integrated leakage rate tests are performed at or above 49.4 psig or at or above 24.7 psig for the reduced pressure test program. The leak rate will be calculated using the formulas of Reference 2 (Total Time) and Reference 3 (Mass Point).

Test schedules and the acceptance criteria specified herein are established based on the requirements of 10 CFR 50, Appendix J.m()

A containment leakage rate of 0.12 wt%

of the initial content of containment atmosphere at 49.4 psig/24 hours maintains public exposure well below 10 CFR 100 values in the event of a hypothetical LOCA."

This leakage rate also limits public exposure to 10 CFR 100 values even if a complete core meltdown is postulated.

The acceptance criteria for (1) Type A test is 75% of the containment leakage rate specified above (2) Type B and Type C tests combined is 60% of the containment leakage rate specified above.

to allow for possible deterioration of the containment boundary between tests.

II. Recirculation System Testing The portion of the Recirculation system outside the containment sphere is effectively an extension of the boundary of the containment.

SAN ONOFRE - UNIT 1 4.3-5 AMENDMENT NO:

24, 75, 87, 130,

Leatge from this system shall be m tained at as low as practical levels. The effective leakage of this system shall be maintained in accordance with the maximum leakage limitations established in Section 3.3.1.A(4) of Appendix A Technical Specifications.

The piping configurations of the recirculation and containment spray lines assure that leakage within Technical Specification limits will not deplete the isolation valve seal water system fluid inventory for at least 30 days at a pressure of 1.10 Pa. Therefore, leakage from the isolation valves and containment penetrations for these systems is not added to the combined leakage rate for all penetrations and valves subject to Type B and C tests.

The containment penetrations encompassed by the recirculation and containment spray systems include penetrations for one containment spray line, three reactor coolant pump seal water injection lines, and the recirculation pump discharge line to the recirculation heat exchanger.

References (1) 10 CFR 50, Appendix J.

(2) ANSI N45.4-1972 (3) ANSI/ANS 56.8-1981 (4) Final Engineering Report and Safety Analysis, Paragraph 5.3 SAN ONOFRE - UNIT 1 4.3-6 AMENDMENT NO:

75, 87, 130,