ML20003H455
| ML20003H455 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/15/1981 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20003H456 | List: |
| References | |
| NUDOCS 8105060016 | |
| Download: ML20003H455 (7) | |
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o UNITED STATES 8 *I NUCLEAR REGULATORY COMMISSION o
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O TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1
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AMENDHENT TO FACILITY OPERATING LICENSE Amendment No. 5 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) Facility Operating License No. DPR-77, filed by the Tennessee Valley Authority (licensee), dated January 8, February 10, March 3,,and April 2,1981 complies with the standards and require-ments of'the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; 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 Ccmmission; 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 comon defense and security or to the health and safety of the public; and E.
The issuanc.e of this amendment is in accordance with 10 CFR Part 51 af 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 attachments to this license i
amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby a ended to read as follows:
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i 8105060016
. (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 5, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
li 3.
This amended license is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
MW A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing
Attachment:
Appendix A Techi,' cal Specit! cation Changes Date of Isruancei April 15,1981 9
1 ATTACHMENT TO LICENSE AMENDMENT NO. 5 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment rumber and contains vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
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Overleaf Amended Page Page 3/4 6-16 3/4 6-15 B3/4 6-3 83/4 6-3a l
4 SEQUOYAH - UNIT 1 l
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CONT /.INMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM o
LIMITING CONDITION FOR OPERATION 3.6.1.9 One pair (one purge supply line and one purge exhsust line) of con-tainment purge system lines may be open; the containment purge supply and exhaust isolation valves in all other containment purge lines shall be closed.
Operation with purge supply or exhaust isolation valves open for either purging or venting shall be limited to less than or equal to 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> per 365 days.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
With a purge supply or exhaust isolation valve open in excess of the above cumulative limit, or with more than one pair of containment purge system lines open, close the isolation valve (s) in the purge line(s) within one hour or be in at least HOT STANOBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUT 00WN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.1.9.1 The position of the containment purge supply and exhaust isolation valves shall be determined at least once per 31 days.
i 4.6.1.9.2 The cumulative time that the purge supply and exhaust isolation valves are open during the past 365 days shall be determined at least once per 7 days.
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SEQUOYAH - UNIT 1 3/4 6-15 AMENDMENT NO. 5
CONTAINMENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS CONTAINMENT SPRAY SYSTEM LIMITING CONDITION FOR OPERATION 3.6.2.1.Two independent containment spray systems shall be OPERABLE with each spray system capable of taking suction from the RWST and transferring suction to the containment sump.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With one containment spray system ipoperable, restore the inoperable spray system to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the inoperable spray system.to OPERA 3LE status within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.2.1 Eacn containment spray system shall be demonstrated OPERABLE:
a.
A: least once per 31 days by verifying that eacn valve (manual, ccwer operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
i By verffying, that on recirculation flow, eaca ; ump develops a l
c.
ciscnarge pressure of greater than or equal to 140 psig wnen tested oursuant to Specification 4.0.5.
c.
At least once per 18 months du' ring shutdown, cy:
I 1.
Verifying that each automatic valve in tne flow path actuates to its correct position on a Containment Pressure--High-Hign test signal.
2.
Verifying that each spray pump starts automatically on,a l
Containment Pressure--High-High test signal.
At least once per 5 years by performing an air or scoke flow test c.
througn each spray header and verifying each spray no:Ile is unocstructed.
'inese more stringent recuirecents shall remain in effect pending resciution of tre nycrogen control matter.
SEQUOYAH - UNIT 1 3/4 6-16
CONTAINMENT SYSTEMS BASES 3/4.6.1.8 EMERGENCY GAS TREATMENT SYSTEM (EGTS)
The OPERABILITY of the EGTS cleanup subsystem ensures that during LOCA conditions, containment vessel leakage into the annulus will be filtered tnrough the HEPA filters and charcoal'adsorber trains prior to discharge to the atmosphere.
This requirement is necessary to meet the assumptions used in the accident analyses and limit the site boundary radiation doses to within the limits of 10 CFR 100 during LOCA conditions.
Cumulative operation of the system with the heaters on for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31 day period is sufficient to recuce the builcup of moisture on the abscrbers aad HEPA filters.
ANSI N510-1975 will be used as a procedural guide for surveillance testing.
3/4.6.1.9 CONTAINMENT VENTILATION SYSTEM Use of the containment purge lines is restricted to only one pair (one supply line and one exhaust line) of purge system lines at a time to ensure that the site boundary dose guidelines of 10 CFR Part 100 would not be exceeded in the event of a loss of coolant accident during purging operations.
The analysis of this accident assumed purging through the largest pair of lines (a 24 incn inlet line and a 24 inch outlet line), a pre-existing iodine spike in the reactor coolant and four second valve closure times.
3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.1 CONTAINMENT SPRAY SYSTEM The OPERABILITY of the containment spray system ensures that containment depressurization and cooling capability will be available in the event of a LOCA.
The pressure reduction and resultant lower containment leakage rate are consistent with the assumptions used in the accident analyses.
3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERASILITY of the containment isolation valves ensures that,the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurizasion of the containment.
Containment isolation within the time limits specified ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA. By letters dated March 3,1981, and April 2,1981, TVA will submit a report on the operating experience of the plant no later than startup after the first refueling.
This information will be used to proivde a basis to re-evaluate the adequacy of the purge and vent tine limits.
SEQUDYAH - UNIT 1 B 3/4 6-3 AMENDMENT NO. 5
CONTAlfsMENT SYSTEMS BASES 3/4.6.4 CCMSUSTIBLE GAS CCNTROL The OPERASILITY of the equipment and systems required for the detection.
anc control of hycregen gas. ensures that this cquipment will be availacia to maintain the hydrogen concentration within containment below its flamacle limit during post-LOCA conditions. Either recombiner unit or the purge systes n
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l SEQUOYAH - UNIT 1 B 3/4 6-3a A"E?CMENT NO. 5
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