ML20235U970
| ML20235U970 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/28/1989 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235U974 | List: |
| References | |
| NUDOCS 8903090459 | |
| Download: ML20235U970 (12) | |
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l TENNESSEE VALLEY AUTHORITY DOCKET N0. 50-327 SEOU0YAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.101 License No. DPR-77 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by-Tennessee Valley Authority (the licensee) dated August 10, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
i 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 o# 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 (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment wil.1 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.
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i ATTACHMENT TO LICENSE AMENDMENT NO. 101' FACILITY OPERATING ~ LICENSE N0. DPR-77 L
DOCKET NO. 50-327, Revise the Appendix A Technical Specifications by removing the pages identified below-and inserting the enclosed pages. The revised pages dre identified by the captioned amendment number and contain marginal lines indicating the area of change. Overleaf pages* are provided to inaintain document completeness.
REMOVE INSERT 3/4 6-3 3/4 6-3*
3/4 6-4 3/4 6-4 3/4 6-18 3/4 6-18 3/4 6-23 3/4 6-23 i
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CONTAINMENT' SYSTEMS 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 speci-fied in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972:
a.
Three Type A tests (0verall Integrated Containment Leakage Rate) shall be conducted at 40 + 10 month intervals during shutdown at P a (12 psig) during each 10 year service period.
The third test of each set shall be conducted during the shutdown for the 10 year plant inservice inspection.
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 a Type A test shali be performed at least every 18 months until two consecutive Type A tests meet 0.75 L at which time the above test a
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
- a 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 Pa (I2 psi 9)*
SEQUOYAH - UNIT 1 3/4 6-3
^
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) d.
Type B and C tests shall be conducted with gas at Pa (12 psig) at intervals no greater than 24 months except for tests involving:
1.
Air locks, i
2.
Penetrations using continuous leakage monitoring systems, and 3.
Valves pressurized with fluid'from a seal system.
e.
The combined bypass leakage rate to the auxiliary building shall be I
determined to be less than or equal to 0.25 L, by applicable Type B and C tests at least once per 24 months except for penetrations which are not individually testable; penetrations not individually testable shall be determined to have no detectable leakage when tested with soap bubbles while the containment is pressurized to P, (12 psig)-
during each Type A test.
f.
Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.
g.
Leakage from isolation valves that are sealed with fluid from a seal system may be excluded, subject to the provisions of Appendix J,Section III.C.3, when determining the combined leakage rate provided the seal system and valves are pressurized to at least 1.10 P, (13.2 psig) and the seal system capacity is adequate to maintain system pressure (or fluid head for the containment spray system and RHR spray system valves at penetrations 48A, 488, 49A and 498) for at least 30 days.
h.
Type B tests for penetrations employing a continuous leakage monitoring system shall be conducted at Pa (12 psig) at intervals no greater than once per 3 years.
1.
All test leakage rates shall be calculated using observed data converted to absolute values.
Error analyses shall be performed to select a balanced integrated leakage measurement system.
j.
The provisions of Specification 4.0.2 are not applicable.
i SEQUOYAH - UNIT 1 3/4 6-4 Amendment No.
12, 71, 101 iL______.__.______..___.__.--__.__
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CONTAINME'NT. SYSTEMS -
SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.2. Each isolation valve specified in Table 3.6-2 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:
a.
Verifying that on a Phase A' containment isolation. test signal, each Phase A isolation valve actuates to its isolation position.
b.
Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve actuates to its isolation position.
c.
Verifying that on a Containment Ventilation isolation test signal, each Containment Ventilation Isolation valve actuates to its isolation position.
d.
Verifying that on a high containment pressure isolation test signal, each Containment Vacuum Relief Valve actuates to its isolation position.
e.
Verifying that on a Safety Injection test signal that the Normal Charging Isolation valve actuates to its isolation position.
4.6.3.3 The isolation time of each power operated or automatic valve of Table 3.6-2 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.
~4.6.3.4 Each Containment Purge isolation valve shall be demonstrated OPERABLE within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after each closing of the valve, except when the valve is being used for multiple cyclings, then_at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, by verifying that when the measure leakage rate of these valves is added to the leakage rates determined pursuant to Specification 4.6.1.2.d for all other Type B and C penetrations, the combined leakage rate is < 0.60 L
- a SEQUOYAH - UNIT 1 3/4 6-18 Amendment No. 12, 81, 101
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SE0VOYAH NUCLEAR PLANT, UNIT 2 AMENDf/ENT TO FACILITY OPERATIt;G LICENSE Amandment No. 90 License No. DPR-79 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated August 10, 1988, ccmplies 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 (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will r,ct te inirsicel to the ccirson defense and security or to the health and safcty cf the public; and E.
The issuance of this amendment is in accoraance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
1 l
^ 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 License No. DPR-79 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 90, 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 d
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Suzanne Black, Assistant Director for Projects TVA Projects Division Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 28, 1989
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ATTACHMENT TO LICENSE AMENDMENT NO. 90 FACILITY OPERATING 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. Overleaf pages* are provided to maintain document completeness.
REMOVE INSERT 3/4 6-4 3/4 6-4 3/4 6-18 3/4 6-18 3/4 6-23 3/4 6-23
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) l 3.
Valves pressurized with fluid from a seal system.
e.
The combined bypass leakage rate to the auxiliary building shall be determined to be less than of equal to 0.25 L, by applicable Type B and C tests at least once per 24 months except for penetrations which are not individually testable; penetrations not individually testable shall be determined to have no detectable leakage when tested with soap bubbles while the containment is pressurized to P, 12 psig, 3
during each Type A test.
f.
Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1 3.
g.
Leakage from isolation valves that are sealed with fluid from a seal system may be excluded, subject to the provisions of Appendix J,Section III.C.3, when determining the combined leakage rate provided the seal system and valves are pressurized to at least 1.10 P,, 13.2 psig, and the seal system capacity is adequate to maintain system pressure (or fluid head for the containment spray system and RHR spray system valves at penetrations 48A, 48B, 49A and 49B) for at least 30 days.
h.
Type B tests for penetrations employing a continuous leakage monitoring system shall be conducted at P, 12 psig, at intervals no 3
greater than once per 3 years.
i.
All test leakage rates shall be calculated using observed data converted to absolute values.
Error analyses shall be performed to select a balanced integrated leakage measurement system.
j.
The provisions of Specification 4.0.2 are not applicable.
SEQUOYAH - UNIT 2 3/4 6-4 Amendment No. 63, 90
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.6.3.2 Each isolation valve specified in Table 3.6-2 shall be demonstrated OPERABLE during the COLD SHUTDOWN or REFUELING MODE at least once per 18 months by:
a.
Verifying that on a Phase A containment isolation test signal, each Phase A isolation valve actuates to its isolation position.
b.
Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve actuates to its isolation position.
c.
Verifying that on a Containment Ventilation isolation test signal, each Containment Ventilation valve actuates to its isolation position.
I d.
Verifying that on a high containment pressure isolation test signal, each Containment Vacuum Relief Valve actuates to its isolation position.
e.
Verifying that on a Safety Injection test signal that the Normal Charging Isolation valve actuates to its isolation position.
4.6.3.3 The isolation time of each power operated or automatic valve of
-Table 3.6-2 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.
4.6.3.4 Each containment purge isolation valve shall be demonstrated OPERABLE within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after each closing of the valve, except when the valve is being used for multiple cyclings, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, by verifying that when the measured leakage rate is added to the leakage rates determined pursuant to Specification 4.6.1.2d. for all other Type B and C penetrations, the combined leakage rate is less than or equal to 0.60 L,.
i SEQUOYAH - UNIT 2 3/4 6-18 Amendment No. 72, 90
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