ML20070B550
| ML20070B550 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/29/1991 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070B553 | List: |
| References | |
| NUDOCS 9101310234 | |
| Download: ML20070B550 (5) | |
Text
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s TENNESSEE VALLEY AUTHORITY P0CKET NO. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT "1 FACILITY OPERATING LICENSE Amendment No.139 License No. OPR-79 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated August 31, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (11) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
9101310234 910129 PDR ADOCK 05000329 P
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating Licerise No. DPR-79 is hereby amended to read ss follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.139, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION sr$.-
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Frederick J. Hehon Director Project Directorate 11-4 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 29, 1991 l
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ATTACHMENT TO LICENSE AMENDMENT N0.139 FACILITY OPERATif[G_ LICENSE NO. DPR-79 DOCKET NO. 50-328 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3/4 6-3 3/4 6-3 B3/4 6-1 B3/4 6-1 1
I
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i CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstra'.ed at the following test schedule and shall be dett!rmined in conformance with the criteria speci-fied in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972; however, the methods of ANSI /ANS 56.8-1987 for mass point data analysis may be used in lieu of the methods specified in ANSI N45.4-1972.
a.
Three Type A tests (Overall Integrated Containment Leakage Rate) 1 shall be conducted at 40 1 10-month intervals during shutdown at P,,12 psig, during each 10 year service period, b.
If any periodic Type A test fails to meet 0.75 L, the test schedule j
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 l
consecutive Type A 13sts meet 0.75 L, at which time the above test schedule may be resumed.*
c.
The accuracy of each Type A test shall be verified by a supplemental test which:
1.
Confirms the accuracy of the Type A test by verifying that the difference between supplemental and Type A test data is within 0.25 L,.
2.
Has a duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.
3.
Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be equivalent-to at least 25 percent of the total measured leakage
.at P,, 12 psig, d.
Type B and C tests shall be conducted with gas at P, 12 psig, at a
intervals no greater than 24 months except for tests involving:
1.
Air locks, 2.
Penetrations using continuous leakage monitoring systems, and.
3.
Values pressurized with fluid from a seal system.
- An exemption from the 18-month accelerated frequency requirement is allowed for the Type A test failures conducted during the Unit 2 Cycle 2 and Unit 2 Cycle 3 refueling outiges-SEQUOYAH - UNIT 2 3/4 6-3 Amendment No. 91, 126, 139
3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1 PRIMARY CONTAINMENT Primary CONTAINMENT INTEGRITY ensures that the release of radioactive 4
materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses.
This restriction, in conjunction with the leakege 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, P,.
As an added conservatism, the measured overall integrated leakage rate is further limited to less than or l
equal to 0.75 L, during performance of the periodic tests to account for possible degradation of the containment leakage barriers between leakage tests.
l The surveillance testing for measuring leakage rates are consistent with the requirements of Appendix "J" of 10 CFR 50 with the following exemption:
the third Type A test of each 10 year inservice interval need not be conducted when the plant is shut down for the 10 year plant _ inservice inspection.
Due to l
the increased accuracy of the mass point-method for containment integrated j
leakage testing, the mass point method referenced in ANSI /ANS 56.8-1987 can be used in lieu of the methods described in ANSI N45.4-1972.
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 provide 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 INTERNAL-PRESSURE l
The limitations on containment internal pressure ensure that 1) the containment structure is prevented from exceeding its design negative pressure differential with respect to the annulus atmosphere of 0.5 psig and 2) the-l SEQUOYAH - UNIT 2 B 3/4 6-1 Amendment No. 91, 139 l-
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