ML19321A859
| ML19321A859 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 07/10/1980 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19321A856 | List: |
| References | |
| NUDOCS 8007240302 | |
| Download: ML19321A859 (4) | |
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UNITED STATES j
NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20655
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,o TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQU0YAH NUCLEAR PLANT, UNIT 1 FACILITY LICENSE Amendmerit No. 4 License No. DPR-77 1.
The Nuclear Regulatory Comission (the Comission) having found that:
A.
The application for amendment to the Sequoyah Nuclear Plant, Unit 1 (the facility) license, DPR-77, filed by the Tennessee Valley Authority (licensee), dated April 9,1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; 8.
The facility will operata in Conformity with the license, as amended, the provisions of the Act, and the rules and regulations of the Comission-C.
There is reasonable assurence (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (iii that such activities will be con-ducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public, and j
E.
The issuance of tnis amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is hereby amended by page changes to the Appendix A Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:
8007240302 j
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- i. (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 4, are hereby incorporated into the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This amended license is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Harold R. Denton, Director Office of Nuclear Reactor Regulation
Attachment:
Appendix A Technical Specification changes Date of Issuance:
JUL 101980 i
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i ATTACHeiENT TO LICENSE AMEN 0 MENT NO. 4 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page.
The revised page is identified by Amendment number and contains a vertical line indicating the area of change.
Page 8-1 l
SEQUOYAH - UNIT 1 i
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8.1 SPECIFICATION 3/4.11.1 Prior to initial criticality, the requirements for sampling and analysis for items A.6, A.7, and A.9 in Table 4.11-1 may be waived provided the release is through the turbine building sump (item 8.2 of the Table 4.11-1).
8.2 SPECIFICATION 4.8.1.1.2c The surveillance requirements for verifying diesel generator voltage and frequency during diesel generator starts is waived for the original surveillance interval only.
8.3 SPECIFICATION 4.7.8.1, ITEM 0 3 The 1/4 inch negative pressure requirement within the spent fuel storage area and ESF pump rooms is waived during the low power test program.
However, the auxiliary building gas treatment system shall be capable of maintaining these areas at a slight negative pressure during this period.
8.4 SPECIFICATION 3.3.3.10, TABLE 3.3-13, ACTION 41 Flow rates for ventilation systems for the shield building exhaust, auxiliary building and service building may be estimated using the design flow rate for the appropriate fans.
This interim waiver extends the 30-day limit for 18 months from the issuance of this license.
This waiver is considered to be an interim measure until flow rate monitors for the ventilation system for these structures can be repaired or replaced.
8.5 SPECIFICATIONS 3.5.2, 3.5.3, 3.6.2.1, 3.6.3.1, and 3.7.1.2 Prior to initial criticality, the provisions of Specification 3.0.4 are not applicable when system inoperability has been determined solely on unresolved _ piping support or restraint deficiencies.
8.6 LOW POWER TEST PROGRAM For the conducting of the low power test program only, the licensee has been granted an exception from the requirements of those Technical Specifications identified in Table 3.1 of our Safety Evaluation Report dated, July 10, 1980, related to the Special Low Power Test Program.
SEQUOYAH - UNIT 1 8-1 Amendment !!o. 2,J,4
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