B12784, Proposed Tech Specs,Revising Integrated Leak Rate Test
| ML20235A644 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 01/05/1988 |
| From: | NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20235A633 | List: |
| References | |
| B12784, NUDOCS 8801120374 | |
| Download: ML20235A644 (3) | |
Text
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i Docket No. 50-336 B1278_4 I
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ATTACHMENT 1 Millstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Specifications Integrated Leak Rate Test 1
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January 1988 n-
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August 1, 1975 CONTAINMENT SYSTEMS CQFTAINMENT 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 percentbyweightofthecontainmentairher24 hours at P, 54 psig.
a b.
A combined leakage rate of 5 0.60 L for all penetra-tions and valves subject to Type B $nd C tests when pressurized to P
- a c.
A combined leakage rate of 5 0.017 L for all penetra-tions identified in Table 3.6-1 as s8condary contain-ment bypass leakage paths when pressurized to P
- a APPLICABILITY: MODES 1, 2,
3 and 4.
ACTION:
l With either (a) the measured overall integrated containment leakage rate for all penetrations an(b) with the measured combined leakage rate exceeding 0.75 L, or d valves subject to Types B and C tests exceeding 0.60 L, or (c) with the combined bypass a
leakage rate exceeding 0.017 L, restore the leakage rate (s) to within the limit (s) prior to i$ creasing 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 confor-mance with the criteria specified in Appendix J of 10 CFR 50.
a.
Three Type A tests (Overall Integrated Containment Leakage Rate) shr.ll be conducted at 40 i 10 month intervals during shutdown at P (54 psig) during each 10-year service period.
The tSird test of each set shall be conducted during the shutdown for the 10-year plant inservice inspectioli.
MILLSTONE - UNIT 2 3/l, 6-2
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August 1, 1975 3/4.6 CONTAINMENT SYSTEMS BASES 1
3/4.6.1 PRIMARY CONTAINMENT l
3 & 6.1.1 CONTAINMENT INTEGRITY J
Primary CONTAINMENT INTEGRITY ensures that the release of I
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 _ CON _TAINMENT LEAKAGE The limitations on containment leakage rates' ensure that'the i
total containment leakage volume will'not exceed the value assumed inLthe accident analyses at the peak accident pressure of 54 psig, P.
As an added conservatism, the measured overall a
' integrated leakage rate is further limited to 5 0.75 L during performance of-the periodic tests to account for possi8le 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.
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 leskage will not become excessive through continusus usage.
MILLSTONE - UNIT 2 B 3/4 6-1 L
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