ML20073H089

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Proposed Tech Specs SR 4.6.1.2.a,permitting More Flexible Schedule for Containment Leakage Type a Testing
ML20073H089
Person / Time
Site: Millstone Dominion icon.png
Issue date: 09/28/1994
From:
NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20073H087 List:
References
NUDOCS 9410050114
Download: ML20073H089 (10)
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Text

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. Docket No. 50-423 l B14981 Attachment 1 Millstone Nuclear Power Station, Unit No. 3 Proposed Revision to Technical Specifications Containment Leakage Type A Test Schedule ,

Marked-up Pages I

i l

September 1994 l

l 9410050114 940928 i PDR ADOCK 05000423 P PDR i l

CONTAlletENT. SYSTDt$

03/24/M CONTAllBIENT LEAKARE i LIMITING CONDITION FOR OPERATION s

i 3.6.1.2 Containment leakage rates shall be limited to: I i

a. An overall integrated leakage rate of less than or equal to L.,

0.31G 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 P.,

53.27 psia (38.57 psig);

b. A combined leakage rate of less than 0.60 L, for all penetrations and valves subject to Type B and C tests, when pressurized to P,;

and i

c. A combined leakage rate of less than or equal to 0.042 L, for all l penetrations that are SECONDARY CONTAINMENT BOUNDARY bypass leakage paths when pressurized to P . i APPLICABILITY: MODES I, 2, 3, and 4.

ACTION:

With the seasured overall integrated containment leakage rate exceeding 0.75 L., or the measured combined leakage rate for all penetrations and valves subject to Type B and C tests exceeding 0.60 L , or the combined bypass ,

leakage rate exceeding 0.042 L., restore the overall integrated leakage rate "'

to less than 0.75 L., the combined leakage rate for all penetrations subject .

to Type B and C tests to less than 0.60 L., and the combined bypass leakage rate to less than 0.042 L, prior to increasing the Reactor Coolant System temperature above 200*F.

SURVEILLANCE REQUIRENENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following L test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR Part 50 using methods and provisions of ANSI N45.4-1g72 (Total Time Method) and/or ANSI /ANS 56.8-1981 (Mass Point Method):

a. Three Type A tests (Overall Integrated Containment Leakage Rate) g,%

shall be conducted at 40110 month intervals during shutdown at a ,

pressure not less than P., 53.27 psia (38.57 psig) during each w 10-year service period. The third test of each set shall be y conducted during the shutdown for the 10-year plant inservice inspection; _

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b. If any periodic Type A test fails to meet 0.75 L for subsequent Type A tests shall be revieweddan., the test approved by the schedule Commission. If two consecutive Type A tests fail to meet 0.75 L., a Type A test shall be performed at least every 18 months until two .i

' consecutive Type A tests meet 0.75 L, at which time the above test schedule my be resumed; "

MILLSTONE - UNIT 3 3/4 6-2 Amendment No. JJ. 57, 89, l em

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.  % 03/24/94 3/4.6 CONTAtlMENT SYSTEMS

( Sk3E5 5/4.6.1 PRIMARY C0f(TAINNENT 1/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the safety analyses. This restric-tion, in conjunction with the leakage rate limitation, will limit the SITE BDUNDARY radiation doses to within the dose guidelines of 10 CFR Part 100 during accident conditions and the control room operators dose to within the guidelines of GDC 19.

3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates. ensure that the total containment leakage volume will not exceed the value assumed in the safety analyses at the peak accident pressure, P,. As an added conservatism, the measured overall integrated leakage rate is further limited to less than or equal to 0.75 L. during performance of the periodic test to account for possible degradation of the containment leakage barriers between leakage tests.

The surveillance testing for measuring leakage rates are consistent with the requirements of Appendix J of 10 CFR Part 50 6TN5ERT 'x' The enclosure building bypass leakage paths are listed in Operating Procedure 3273, " Technical Requirements - Supplementary Technical Specifica-tions." The addition or deletion of the enclosure building bypass leakage paths shall be made in accordance with Section 50.59 of 10CFR50 and approved by the Plant Operation Review Committee.

3/4.6.1.3 CONTAINMENT AIR LOCKS 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 lock seals provides assurance that the overall air lock leakage will not become excessive due to seal damage '

l during the intervals between air lock leakage tests.

3/4.6.1.4 and 3/4.6.1.5 AIR PRESSURE and AIR TEMPERATURE The limitations on containment pressure and average air temperature ensure that: (1) the containment structure is prevented from exceeding its design negative pressure of 8 psia, and (2) the containment peak pressure does 8 3/4 6-1 > Amendment No. M. 89, g R!jlSTONE-UNIT 3 l

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Docket No. 50-423 B14931 l

t Attachment 2  !

Millstone Nuclear Power Station, Unit No. 3 Proposed Revision to Technical Specifications Containment Leakage Type A Test Schedule Retyped Pages i

f

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i I

September 1994  ;

l

._______-_A

r CONTAINNENT SYSTEMS CONTAINNEKf LEAKAGE LINITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:

a. An overall integrated leakage rate of less than or equal to L.,

O.3% 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 P.,

53.27 psia (38.57 psig);

b. A combined leakage rate of less than 0.60 L, for all penetrations and valves subject to Type B and C tests, when pressurized to P,;  !

and ,

c. A combined leakage rate of less than or equal to 0.042 L, for all penetrations that are SECONDARY CONTAINMENT B0UNDARY bypass leakage paths when pressurized to P,.

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

ACTI0ti:

With the measured overall integrated containment leakage rate exceeding 0.75

  • L., or the measured combined leakage rate for all penetrations and valves subject to Type B and C tests exceeding 0.60 L., or the combined bypass leakage rate exceeding 0.042 L , restore the overall integrated leakage rate ,

to less than 0.75 L., the combined leakage rate for all penetrations subject to Type B and C tests to less than 0.60 L., and the combined bypass leakage rate to less than 0.042 L, prior to increasing the Reactor Coolant System -

temperature above 200*F.  !

SURVEILLANCE REQUIREMENTS r

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 Part 50 using methods and provisions of ANSI  !

N45.4-1972 (Total Time Method) and/or ANSI /ANS 56.8-1981 (Mass Point Method):

a. Three Type A tests (0verall Integrated Containment Leakage Rate) shall be conducted at approximately equal intervals during shutdown '

at a pressure not less than P , 53.27 psia (38.57 psig), during each 10-year service period.*

b. If any periodic Type A test fails to meet 0.75 L,, the test schedule for subsequent Type A tests shall be reviewed and approved by the ,

Commission. If two consecutive Type A tests fail to meet 0.75 L , a Type A test shall be performed at least every 18 months until two consecutive Type A tests meet 0.75 L, at which time the above test schedule may be resumed;

  • The third Type A test will be conducted during the sixth refueling outage. As i a result, the duration of the first 10-year service period will be extended to the end of the sixth refueling outage.

NILLSTONE - UNIT 3 3/4 6-2 Amendment No. J7, 77, 77, I l

I

._-________ _ -_ ___ _ - - _a

3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the safety analyses. This restric-tion, in conjunction with the leakage rate limitation, will limit the SITE B0UNDARY radiation doses to within the dose guidelines of 10 CFR Part 100 during accident conditions and the control room operators dose to within the guidelines of GDC 19. ,

3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the safety  :

analyses at the peak accident pressure, P,. As an added conservatism, the t measured overall integrated leakage rate is further limited to less than or equal to 0.75 L, during performance of the periodic test to account ,

for possible degradation of the containment leakage barriers between leakage tests.

The surveillance. testing for measuring leakage rates are consistent with the requirements of Appendix J of 10 CFR Part 50. A partial exemption has been granted from the requirements of 10CFR50, Appendix J, Section III.D.1(a). The exemption removes the requirement that the third Type A test for each 10-year 8 period be conducted when the plant is shut down for the 10-year plant inservice t inspection (Reference License Amendment No. ). ,

The enclosure building bypass leakage paths are listed in Operating ,

Procedure 3273, " Technical Requirements - Supplementary Technical Specifica-tions." The addition or deletion of the enclosure building bypass leakage paths shall be made in accordance with Section 50.59 of 10CFR50 and approved  ;

by the Plant Operation Review Committee.

3/4.6.1.3 CONTAINMENT AIR LOCKS '

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 lock seals provides assurance that '

the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.

3/4.6.1.4 and 3/4.6.1.5 AIR PRESSURE and AIR TEMPERATURE

~

The limitations on containment pressure and average air temperature '

ensure that: (1) the containment structure is prevented from exceeding its design negative pressure of 8 psia, and (2) the containment peak pressure does ,

MILLSTONE - UNIT 3 B 3/4 6-1 Amendment No. J7, 77, f 0289 l

i f

Docket No. 50-423 B14981 i f

i 1

i Attachment 3 f Millstone Nuclear Power Station, Unit No. 3 Proposed Revision to Technical Specifications Containment Leakage Type A Test Schedule Timeline for the First 10-Year Service Period l

1 l

September 1994 l

l l

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TIMELINE FOR THE FIRST 10-YEAR SERVICE PERIOD Without Approval of Technical Specification Revision and Grant of Appendix J Exemption Request 1985 (7/85) Pre-Operational Type A Test Performed --*

86

  • - (4/86) First 10-Year Inservice Inspection Period Begins 9 Months After Pre-Operational Type A Test 87 88 (7/5/89) First Type A Test for the First 10-Year 89 Service Period Conducted 48 -*

Months After the Pre-Operational -

Type A Test 50 91 92 (10/12/93) Second Type A Test for the First 93 10-Year Service Period Conducted 51  !

Months After the First Type A Test -*

94 (4/95) Third Type A Test for the First 10-Year 95 Service Period Scheduled to be Conducted 18 Months After Second Type A Test --> .- (4/95) Inservice inspection for the  !

During the Fifth Refueling Outage First 10-Year Service Period  ;

Will Be Completed During the ,

(7/95) Third Type A test for the first 10-year -* Fifth Refueling Outage service period has to be performed to comply with Appendix J.

{ 96 1

  • - (4/96) Third Type A Test of First i I

10-Year Service Period Has to be Performed by this Date to Comply with Appendix J and Technical Specification 4.6.1.a ,

(4/97) Fourth Type A Test for the First 10-Year l j Service Period Would Have to be Performed 97 l

i to Comply with Technical Specification -*

4.6.1.2.a l

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