ML20028C064
| ML20028C064 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/27/1982 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20028C065 | List: |
| References | |
| NUDOCS 8301050504 | |
| Download: ML20028C064 (4) | |
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1_
AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 23 License No. DPR-77 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications 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 May 25, August 6, August 12, Septeinber 9, and November 22, 1982, comply with the standards and requirements of the istomic 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 Com-mission; 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 (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.
2.
Accordingly, Facility Operating License DPR-77 is amended by the following changes:
A.
Change paragr1ph 2.C.(18)(c) to read as follows:
(c) At the first outage of sufficient duration but no later than startup following the second refueling outage TVA shall have installed, demonstrated operable, proposed appropriate Technical Specifications, and received NRC approval for an additional level of over/undervoltage protection acceptable to the NRC staff.
The level of protection from the effects of power transients on safety-related equipment provided by Pa. t ' ef Um aiaii's W coded drio iuico9e Fur W uo, or eym va-f
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Change paragraph 2.C.(20) to read as follows:
(20) Low Temperature Overpressure Protection (Section 5.2.2) x At the first outage of sufficient duration but no later than s.
01 startup following the second refueling outage, TVA shall install S
an overpressure mitigation system which meets NRC requirements. '
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C.
Change paragraph 2.C.(22)C. to read as follows:
C.
Control Room Design (Section 22.2.1.D.1)
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TVA shall consider the benefits of installing data recording H,f and logging equipment in the control room to correct the deficiencies associated with the trending of important parameters on strip chart recorders used in the control room as part of the Detailed Control Room Design Review.
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tation shall be carried out in accordance with SECY 82-1118.
N D.
Change paragraph 2.C.(23)E. to read as follows:
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E.
Reactor Coolant System Vents (Section 22.3, II.B.1)
At the first outage of sufficient duration but no later than startup following the second refueling outage. TVA shall install reactor coolant system and reactor vessel head highpoint vents e
that are remotely operable from the control room.
E.
Change paragraph 2.C.(23)D.(2) to read as follows:
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.(2)
At the first outage of sufficient duration but no later'than' '
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the following qualified monitoring instrumentation:
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(a) Integrated monitoring assembly which will a:complish particulate, iodine and noble gas monitoring.
Qx (b) Containment high range radiation monitor.
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(c) Containment pressure monitor.
(d) Containment water level monitor.
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(e) Containment hydrogen monitor.
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F.
Change paragraph 2.C.(23)H.(2) to read as follows:
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. t3 (2)
At the first outage of sufficient duration but no later than startup following the second refueling outage, TVA shall installs reactor vessel water level instrumentation which meets *NRC (
requirements.
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Ch ange $3ragraph 2.C.(23)F. to year / as follows:
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Post Accident Sacoling-(Eection 22.3, II.B.3) t u*
N At the first outade of' sufficient duration but no later than 1-
startyp following the'second refueling outage. TVA shall com-s.
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.blete corrective actions needed to provide the capability to N
i'i promptly obtaid and perfordi radioisotopic and chemical analysis i
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of reactor coo)' ant and conta*nment atmosphere samples under J'
degraded core conditions with excessive exposure.
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- 41. Ma' ige paragraph 2.C.(23)l.(1) to read as follows:
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(1)
At the first. outage of sufficient duration but no later than s
startup following the second refueling outage, TVA shall update
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the Technical Support Facilities to meet NRC requirements.
3.
This license amendment is effective as of its date of issuance.
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C, FOR THE flVCLEAR REGULATORY COMMISSI'ON
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s Darrell G. Eisenhut, Director
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Division of Licensinn
.Dffica of Nuclear Reactor Rcgulation Date of issuance: December 27, 1982 1
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. B.
Change paragraph 2.C.(20) to read as follows:
(20) Low Temperature Overpressure Protection (Section 5.2 At the first outage of sufficient duration but er than startup following the second refueling outage shall install an overpressurc mitigation system which mee requi rements.
C.
Change paragraph 2.C.(22)C. to read as foll F
C.
Control Room Design (Section 22.2.
.1)
(At the-first-outage-of-suffici 1ura on but'10 iater i. nan stactu,wfoHowing-the secone tin 3 vui. ave.]-TVA-shall-com-plete the_ detailed-Control
, asige Review e As pert of this-review, TVA shall c der #[lienefits of installing data'.
>>yrecording and logging pment in che control room to correct 9j' the deficiencies ass ed with the trending of important parameters on stri rt recorders used in the control roome s WQ ff(d
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Change paragra h 2.C.(23. to read as follows:
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E.
Reactor Coola d ystem Yents (Section 22.3, II.B.1)~
At the first tage of suffit. lent duration but no later than startup foi owing the second refueling outage, TVA shall install reactor,c lant systen and reactor vessel head highpoint vents that are remotely operable from the control room.
E.
Change parh aph 2.C.(23)D.(2) to read as follows:
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(2)
,At he first outage of sufficient duration but no.later'than s artup following the second refueling outage. TVA shall install he fallowing qualifled monitoring instrumentation:
(a)
Integrated monitoring assembly which will accomplish particulate, iodine and noble gas monitoring.
(b) Containment high range radiation monitor.
c Containment pressure monitor.
d Containment water level monitor.
e Containment hydrogen monitor.
F.
Change paragraph 2.C.(23)H.(2) to read as follows:
(2)
At the first outage of sufficient duration but no later than startup following the second refueling outage. TVA shall install reactor vessel water level instrumentation which meets NRC requirements.
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