ML19320C811
| ML19320C811 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 07/01/1980 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | Parris H TENNESSEE VALLEY AUTHORITY |
| Shared Package | |
| ML19320C812 | List: |
| References | |
| NUDOCS 8007180061 | |
| Download: ML19320C811 (2) | |
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k UNITED STATES NUCLEAR REGULATORY COMMISSION o
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July 1, 1980 Docket No. 50-327 Mr. H. G. Parris Manager of Power Tennessee Valley Authority 500A Chestnut Street, Tower II Chattanooga, Tennessee 37401
Dear Mr. Parris:
SUBJECT:
ISSUANCE OF AMENDMEn"i N0. 2 TO LICENSE NO. DPR SEQ'J0YAH NUCLEAR PLANT, UNIT 1 The Nuclear Regulatory Commission has issued the encloud Amendment No. 2 to License No. DPR-77.
This amendment approves your proposed changes to Appendix A Technical Speci-fications for the Sequoyah Nuclear Plant, Unit 1, dealing with Action Statements to allow entry into Modes 3 and 4.
The enclosed changes permit operations in these modes with unresolved piping support or restraint deficiencies. These changes were proposed in your letter of May 28, 1980.
Oral authorization was provided on May 24, 1980 to proceed with such changes, based on your May 24, 1980 letter.
A copy of the related safety evaluation supporting Amendment No. 2 to License DPR-77 is enclosed. Also enclosed is a copy of the Federal Register Notice which has been forwarded to the Office of the Federal Register for publication.
Sincerely #
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A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing j
Enclosures:
1.
Amendment No. 2 to License No. DPR-77 2.
Safety Evaluation 3.
Federal Register Notice cc w/ enclosures:
See next page 8007180
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Mr. H. G. Parris Manager of Power Tennessee Valley Authority 500A Chestnut Street Tower 11 l
Chattanooga, Tennessee 37401 cc:
Herbert S. Sanger, Jr., Esq.
General Counsel Tbnnessee Valley Authority 400 Commerce Avenue E llB 33 Knoxville, Tennessee 37902 Mr. H. N. Culver Tennessee Valley Authority 400 Connerce Avenue, 249A HBB Knoxville, Tennessee 37902 Mr. Bob Faas Westinghouse Electric Corperation P. O. Box 355-Pittsburgh, Pennsylvania 15230 Mr. Mark Burzynski Tennessee Valley Authority 400 Chestnut Street Towgr II i
Chattanooga, Tennessee 37401 Mr. J. F. Cox Tennessee Valley Authority 400 Commerce Avenue, W10Cl31C Knoxville, Tennessee 37902 Resident Inspector /Sequoyah NPS c/o U.S. Nuclear Regulatory Commission P. O. Box 699 Hixson, Tennessee 37343
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o UNITED STATES g
NUCLEAR REGULATORY COMMISSION o
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WASHINGTON, D. C. 20555
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 LICENSE N0. DPR-77 AMENDMENT N0. 2 1.
The Nuclear Regulatory Commission (the Commission) 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 March 28, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the license, as amended, 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 (ii) 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 sctisifed.
2.
Accordingly, the license is hereby amended by a page change 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:
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2-(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 2, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
A.
This amended license is effective as of May 24, 1980.
FOR THE NUCLEAR REGULATORY COMMISSION MMff A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing Attachnent :
Appendix A Technical Specification changes Date of Issuance:
July 1, 1980 6
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ATTACHMENT TO LICENSE AMENDMENT NO. 2 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 i
SEQUOYAH - UNIT 1 i
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 B.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 D 3 The 1/4 inch negative pressure requirement within the spent fuel storage area and ESF pump rooms is waived duri7g 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, ITEM 33 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.
j 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 cf Specification 3.0.4 are not applicable when system inoperability has been determined solely on unresolved piping support or restraint deficiencies.
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SEQUOYAH - UNIT 1 8-1 Amendment No. 2
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