ML20045G598

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Proposed Tech Spec 3/4.6.1.2 Re Schedular Requirements for Type a Tests
ML20045G598
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 07/02/1993
From:
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20045G593 List:
References
NUDOCS 9307140177
Download: ML20045G598 (10)
v • d • e


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ATTACHMENT- 2 PROPOSED TECHNICAL . SPECIFICATIONS CHANGES .

NORTH ANNA UNITS 1 AND 2

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VIRGINIA ELECTRIC . AND POWER ' COMPANY -!

'l 9307140177 930702 PDR ADOCK 05000338 IEc, pyg, P

3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 CONTAINMENT CONTAINMENT INTEGRITY UMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

APPLICABILITY: MODES 1,2,3, and 4.

ACTION:

Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour 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 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 />.

SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

a. At least once per 31 days by verifying that all penetrations
  • not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are' closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Table 3.6-1 of Specification 3.6.3.1., and
b. By verifying that each containment air lock is OPERABLE per Specification 3.6.1.3.
c. After each closing of the equipment hatch, by leak rate testing the equipment hatch seals with gas at Pa, greater than or equal to 44.1 psig, and verifying that when the measured leakage rate for these seals is added to the leakage rates determined pursuant to Specification 4.6.1.2.b for all other Type B and C penetrations, the l combined leakage rate is less than or equal to 0.60 La.
d. Each time containment integrity is established after vacuum has been bruken by pressure testing the butterfly isolation valves in the containment purge lines and the containment vacuum ejector line.
  • Except valves, blind flanges, and deactivated automatic valves which are located inside the )

containment and are locked sealed or otherwise sealed in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.

NORTH ANNA - UNIT 1 3/4 61 l

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CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE UMITING CONDmON FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to: l

a. An overall integrated leakage rate of less than or equal to La,0.1 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, at the calculated peak containment pressure Pa.

greater than or equal to 44.1 psig,

b. A combined leakage rate of less than or equal to 0.60 La for all penetrations and valves subject to Type B and C tests, when pressurized to Pa, greater than or equal to 44.1 psig.

APPLICABILITY: MODES 1,2,3, and 4.

ACTION:

With either (a) the measured overall integrated containment leakage rate exceeding 0.75 La or (b) with the measured combined leakage rate for all penetrations and valves subject to Type B and C tests exceeding 0.60 La, restore the overall integrated leakage rate to less than 0.75 La and the combined leakage rate for all penetrations subject to Type B and C tests to less than or equal to 0.60 La prior to increasing the Reactor Coolant System temperature above 200*F.

SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of either ANSI N45.4-1972 for leakage rate point data analysis or ANSI /ANS 56.8-1987 for mass point data analysis with a minimum test duration of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

a. Type A (Overall Integrated Containment Leakage Rate) tests shall be conducted in accordance with the requirements specified in Appendix J to 10 CFR 50.
b. Type B and C tests shall be conducted with gas at Pa, greater than or equal to 44.1 l psig, at intervals no greater than 24 months except for tests involving:
1. Air locks.
2. Penetrations using continuous leakage monitoring systems.

NORTH ANNA- UNIT 1 3/4 6-2

.l CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE SURVEILLANCE REQUIREMENTS

c. Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement l 4.6.1.3.
d. Type B tests for penetrations employing a continuous leakage monitoring system shall be conducted at Pa, greater than or equal to 44.1 psig, at intervals no greater than once per 3 years.
e. All test leakage rates shall be calculated using observed data converted to absolute l values. Error analyses shall be performed to select a balanced integrated leakage measurement system.
f. The provisions of Specification 4.0.2 are not applicable. l l

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,I i NORTH ANNA UNIT 1 3/4 6-3 i

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1 3/4.6 CONTAINMENT SYSTEMS j 3/4.6.1 CONTAINMENT CONTAINMENT INTEGRITY UMITING CONDITION FOR OPERATION 1

3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

APPLICABILITY: MODES 1,2,3, and 4 ACTION:

Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour 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 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 />.

SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated;

a. At least once per 31 days by verifying that all penetrations
  • not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Table 3.6-1 of Specification 3.6.3.1., and
b. By verifying that each containment air lock is OPERABLE per Specification 3.6.1.3.
c. After each closing of the equipment hatch, by leak rate testing the equipment hatch seals with gas at Pa, greater than or equal to 44.1 psig, and verifying that when the measured leakage rate for these seals is added to the leakage rates determined pursuant to Specification 4.6.1.2.b for all other Type B and C penetrations, the l combined leakage rate is less than or equal to 0.60 La-
d. Each time containment integrity is established after vacuum has been broken by pressure testing the butterfly isolation valves in the containment purge lines and the containme>1t vacuum ejector line.
  • Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked sealed or otherwise sealed in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per S2 days.

NORTH ANNA - UNIT 2 3/4 61 i

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e CONTANAENT SYSTEMS CONTAINMENT LEAKAGE UMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to

a. An overe!! integrated leakage rate of less than or equal to La,0.1 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, at the calculated peak containment pressure Pa, greater than or equal to 44.1 psig.
b. A combined leakage rate of less than or equal to 0.60 La for all penetrations and valves subject to Type B and C tests, when pressurized to Pa, greater than or equal to 44.1 psig.

APPLICABILITY: MODES 1,2,3, and 4.

ACTION With either (a) the measured overall integrated containment leakage rate exceeding 0.75 La or (b) with the measured combined leakage rate for all penetrations and valves subject to Type B and C tests exceeding 0.60 La, restore the overall integrated leakage rate to less than 0.75 La and the combined leakage rate for all penetrations subject to Type B and C tests to less than or equal to 0.60 La prior to increasing the Reactor Coolant System temperature above 200'F.

SURVEILLANCE REQUIREMEfSTS I 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformcnce with the criteria specified in Appendix J of 10 CFR CO using the methods and provisions of either ANSI N45.4-1972 for. leakage rate point data analysis or ANSI /ANS-56.8.-1987 for mass point data analysis with a minimum test duration 1 l I of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

a. Type A (Overall Integrated Containment Leakage Rate) tests shall be conducted in accordance with the requirernents specified in Appendix J to 10 CFR 50.
b. Type B and C tests shall be conducted with gas at Pa, greater than or equal to 44.1 l psig, at intervals no greater than 24 months except for tests involving:
1. Air locks.
2. Penetrations using continuous leakage monitoring systems.

NORTH ANNA - UNIT 2 3/4 62

CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE SURVEILLANCE REQUIREMENTS

c. Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement l 4.6.1.3.
d. Type B tests for penetrations employing a continuous leakage monitoring system l shall be conducted at Pa, greater than or equal to 44.1 psig, at intervals no greater than once per 3 years,
e. All test leakage rates shall be calculated using observed data converted to absolute l values. Error analyses shall be performed to select a balanced integrated leakage measurement system.
f. The provisions of Specification 4.0.2 are not applicable. l h

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NORTH ANNA- UNIT 2 3/4 6-3 ,

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ATTACHMENT 3 SIGNIFICANT HAZARDS CONSIDERATION VIRGINIA ELECTRIC AND POWER COMPANY

Significant Hazards Consideration Typo A Test Schedule North Anna Power Station Units 1 and 2 North Anna Technical Specifications 3/4.6.1.2 currently require a set of three containment integrated leakage rate (Type A) tests be performed specifically at 40+10 month intervals during each 10-year service period with the third test of each set performed during the shutdown for the 10-year plant inservice inspection. Appendix J to 10 CFR Part 50 requires that a Type A test of the containment be performed periodically. These tests are required to be scheduled as a set of three tests, to be performed at aooroximatelv eoual intervals. during each 10-year service period with the third test of each set to coincide with the shutdown for the 10-year plant insarvice inspection. While the North Anna Technical Specifications leakage rate teving requirements essentially duplicate the requirements in Appendix J, the Technical Specifications additionally require the Type A test be performed at 40110 month intervals. The Technical Specifications requirement to conduct Type A tests at 40i10 month intervals is too restrictive. Therefore, Virginia Electric and Power Company proposes to delete the detailed surveillance schedule for the Type A tests and instead reference performance of Type A testing in accordance with Appendix J to 10 CFR 50.

In addition, there are several editorial changes being made to this section of the Technical Specifications.

The proposed changes to the Technical Specifications do not involve modifications to any of the existing equipment or affect the operation of any existing systems. The reactor containment system reliability and operation are unchanged and, therefore, remain in accordance with the descriptions found in the UFSAR.'

The proposed Technical Specifications changes do not affect or change any other limiting conditions for operation (LCO) or surveillance requirements in the Technical Specifications and the Basis for the Specifications remains unchanged. Periodic Type A tests will still be performed during tne service life of each unit as required by Appendix J to 10 CFR 50. This proposed changes do not change the number of tests required - only the specific schedule is requested to be removed. -

These proposed changes to the North Anna Power Station Units 1 and 2 Technical Specifications have been evaluated against the criteria described in 10 CFR 50.92 ,

and it has been determined that this proposed amendment to the operating license involves no significant hazards consideration.

The proposed Technical Specifications changes do not affect the assumptions, design parameters, or results of any UFSAR accident analysis. The proposed amendment does not add or modify any existing equipment. The proposed Type A testing schedule will still be consistent with Appendix J to 10 CFR 50. Therefore, the proposed Technical Specifications changes would not involve a significant increase in the probability or consequences of an accident previously evaluated.

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- 'The proposed changes to the Technical Specifications do not involve modifications to any of the existing equipment or affect the operation or design basis of the containment. The proposed changes do not modify the response of the containment during a design basis accident. The proposed changes only remove the restrictive schedule requirements for conducting Type A testing from the Technical Specifications. Therefore, the proposed Technical Specifications changes would not create the possibility of a new or different kind of accident from '

any accident previously evaluated.

Although the changes allow more flexibility in scheduling Type A. tests, the proposed amendment continues to ensure reactor containment system reliability by the periodic tests. Since equipment reliability will be maintained, the proposed Techn:Ual Specifications changes will not involve a significant reduction in margin of safety.

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