ML20197A617
| ML20197A617 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/17/1997 |
| From: | NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20197A613 | List: |
| References | |
| NUDOCS 9712230107 | |
| Download: ML20197A617 (3) | |
Text
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l Docket No.'50-423 B16907 5
Millstone Nuclear Power Station Unit No. 3 Proposed Revision to Technical Specification Containment Systems (PTSCR 3-34-97)
Corrected Bases Section Pages 3/4 6-2 and B 3/4 6-1
't t
December 1997 v
9712230107 971217
- DR: ADOCK 05 4y3
.. CONTAIMDIT SYSTEMS CONTAIMENT 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.,
0.3% 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.,- 38.57 psig; I 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 bypass leakage paths when pressurized to P,.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACl10ff:
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 i
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 i
test schedule and shall be determined in conformance with the critaria 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 (Overall Integrated Containment Leakage Rate) shall be conducted at approximately equal intervals during shutdown at a pressure greater than or equal to P, 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; NILLSTONE - UNIT 3 3/4 6-2 Amendment No. 57, 77, pp, JJJ, 0540
- JJ7,
e 3/4.6 CONTAIWIENT_1YiTIMS 1
l BASES 3/4.6.1 PRIMARY CONTAINNENT 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-i tion, in conjunction with the leakage rate limitation, will limit the SITE BOUNDARY radiation doses to within the dose guidelines of 10 CFR Part 100 i
during accident conditions and the control room operators dose to within the guidelines of GDC 19.
The opening of locked or cealed closed containment isolation valves on an intermittent basis under administrative centrol includes the following considerations:
(1) stationing an operator, who is in constant communication with control room, at the volve controls, (2) instructing this operator to close these valves in an accident situation, and (3) assuring that environmental conditions will not preclude access to close the valves and that this action will prevent the release of radioactivity outside the containment.
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 0.75 L, l during performance of the periodic test to account for possible degradation of the containment leakage barriers between leakage tests.
The Limiting Condition for Operation defines the limitations on containment leakage rates for compliance with 10CFR30, Appendix J.
The leakage rates are verified by surveillance testing in accordance with the requirements of Appendix J.
Although the LCO specifies the leakage rates at accident pressure, P., it is not feasible to perform a test at such an exact value for pressure.
Consequently, the surveillance testing is performed at a pressure greater than or equal to P, to account for test instrument uncertainties and stabilization changes. This conservative test pressure ensures that the measured leakage rates are representative of those which would occur at accident pressure while meeting the intent of the LCO.
This test methodology is consistent with the guidance provided in ANSI /ANS 56.8-1981 for meeting the requirements set forth in Appendix J.
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 rcquirements of 10CFR50, Appendix J, Section III.D.l(a). The exemption removes the requirement that the third Type A test for each 10-year period be conducted-when the plant is shut down for the 10-year plant inservice inspection (Reference License Amendment No. 111).
MILLSTONE - UtilT 3 B 3/4 6-1 Amendment No. J7, pp, JJJ, ow