ML20078B976

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Proposed Tech Specs Re Containment Leakage a Test Schedule
ML20078B976
Person / Time
Site: Millstone Dominion icon.png
Issue date: 10/18/1994
From:
NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20078B971 List:
References
NUDOCS 9410270317
Download: ML20078B976 (10)
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4 Rpeket No. 50-336 B15013 Attachment 1 Millstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Specifications Containment Leakage Type A Test Schedule Marked-up Pages October 1994 9410270317 941018 PDR ADOCK 05000336 P PDR

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Z-tc,-q CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:

a. An overall i-tegrated leakage rate of f L , 0.50 percent by weight of tk containment air per 24 hourf at P,, 54 psig. ,
b. A combined leakage rate of 5 0.60 L for all penetrations and valves subject to Type B and C testf when pressurized to P,.
c. A combined leakage rate of 5 0.017 L for all penetrations .

identified in Table 3.6-1 as secondafy containment bypass leakage paths when pressurized to P,.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L , or (b) with the measured combined leakage rate for all penetrations and, valves subject to Types B and C tests exceeding 0.60 L , or (c) with the combined bypass leakage rate exceeding 0.017 L , restore tfle leakage rate (s) to within the limit (s) prior to increasing the Reactor Coolant System temperature above 200*F.

SUPVEILLANCE RE001REMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in confomance with the criteria n specified in Appendix J of 10 CFR 50. - . ._ y t

a. "Thr Type A tests (Overall Integrated Containment Leakage Ratn at P shall e ucted at 40 10 month intervals
  • during l, i

(54 psig) durihr 10-year service period. The-th test of a

, each set shall be con during the shutdown for the 10-year plant inservice inspection. -

  • The test interval for conducting a Type A test shit 1 extended to allow the second Type A test, within the second ten-year service pe to be on conducted during Cycle 11 refueling outage. This extension expi

, copletio'n of Cycle 11 refueling outage. ---

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zesm n 3/4 6-2 Amendment No. J//. .

_ MILLSTONE - UNIT 2 DlA l i

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~Thru. Typ A 4es+3 (omatt L4e3r.ket Coabe+ Laak. 3e resh )

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h Ts L s ea y 11, 1555 k '1b ~@ j 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 accident analyses. This restriction, in conjunc-tion with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.

3/4.6.1.2 CONTAINMEN"' LIAKAGE The li=itatiens en ecntainment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure cf 54 psig, P . As an added conservatism, the measured overall integrated, leakage rate is further limited to 5 0.75 L during performance of the periodic tests to account for possi$le degra-dation 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 50, with the option of the use of the mass point method for perform-ing leakage calculations.

4 D h ErcT AA 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 leak rate given in Specifications 3.6.1.1 and 3.6.1.2.

The limitations on the air locks allow entry and exit into and out of the containment during operation and ensure through the surveillance testing that air lock leakage will not become excessive through continuous usage.

MILLSTONE - UNIT 2 B 3/4 6-1 Amendment

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Docket No. 50-336 B15013 Attachment 2 Millstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Specifications Containment Leakage Type A Test Schedule Retyped Pages October 1994

CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:

a. An overall integrated leakage rate of 5 L., 0.50 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 P , 54 psig.
b. A combined leakage rate of s 0.60 L, for all penetrations and valves subject to Type B and C tests when pressurized to P,.
c. A combined leakage rate of 10.017 L, for all penetrations identified in Table 3.6-1 as secondary containment bypass leakage paths when pressurized to P .

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L,, or (b) with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 L., or (c) with the combined bypass leakage rate exceeding 0.017 L., restore the leakage rate (s) to within the limit (s) 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.

a. Three Type A tests (Overall Integrated Containment Leakage Tests) shall be conducted at approximately equal intervals during shutdown at a pressure not less than P , 54 psig, during each 10-year service period.* i
  • The third Type A test for the second 10-year period shall be conducted during the thirteenth refueling outage. As a result, the duration of the second 10-year service period will be extended to the end of the thirteenth refueling outage.

MILLSTONE - UNIT 2 3/4 6-2 Amendment No. J7J, JJJ, 0182 k.. .

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 accident analyses. This restriction, in conjunc-tion with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.

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 accident analyses at the peak accident pressure of 54 psig, P,. As an added conservatism, the measured overall integrated leakage rate is further limited to 10.75 L, during performance of the periodic tests to account for possible degra-dation 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 50, with the option of the use of the mass point method for perform-ing leakage calculations.

An 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 period be conducted when the plant is shutdown for the 10-year plant inservice inspections (Reference License Amendment No. ).

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 leak rate given in Specifications 3.6.1.1 and 3.6.1.2. The limitations on the air locks allow entry and exit I into and out of the containment during operation and ensure through the surveillance testing that air lock leakage will not become excessive through continuous usage.

MILLSTONE - UNIT 2 B 3/4 6-1 Amendment No. J7f, 0163

4 e

Docket No. 50-336 B15013 Attachment 3 Millstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Specifications Containment Leakage Type A Test Schedule Timeline for the Second 10-Year Service Period i

l I

l l

I October 1994

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. TIMELINE FOR THE SECOND 10-YEAR SERVICE PERIOD Without Approval of Technical Specification Revision and Grant of Appendix J Exemption Request 1985 (6/85) Second 10-Year Appendix J -*

Service Period Began

  • - (12/85) Second 10-Year Inservice Inspection Period Began 86 87 (2/8/88) First Type A Test for the Second -, 88 10 Year Service Period Was -

Conducted 32 Months After Previous Type A Test 89 90 91 92 (12/24/92) Second Type A Test for the Second -+

10-Year Service Period Conducted 58 Months After the First Type A Test 93 94 (10/94) Third Type A Test Scheduled to be Plant inservice Conducted During Twelfth Refueling Inspections for the Outage (Less Than 30 Months Second 10-Year Service Af ter the Second Type A Test) -> *- (10/94) Period Will Be Completed During the Twelfth Refueling Outage (6/95) Second 10-Year Service Period for 95 Appendix J ends. (Third Type A -*

Test must be Performed by This date to Comply with Appendix J)

(10/96) Fourth Type A Test for the Second *- (12/95) Second 10-Year 10-Year Service Period Would Have 96 Inservice inspection to be Performed During the Interval Ends (10-Year Thirteenth Refueling Outage to ISI previously performed Comply with Technical Specification during Twelfth Refueling 4.6.1.2.a -> Outage - 10/94) 97

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