ML20079K449

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Amends 20 & 10 to Licenses DPR-77 & DPR-79,respectively, Revising Tech Spec Re Max Isolation Time for Isolation Valves & Modifying Surveillance Requirements for Penetration Protective Fuse Testing
ML20079K449
Person / Time
Site: Sequoyah  
(DPR-77-A-020, DPR-77-A-20, DPR-79-A-010, DPR-79-A-10)
Issue date: 12/23/1982
From: Adensam E
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20079K451 List:
References
NUDOCS 8301070496
Download: ML20079K449 (11)
v • d • e


Text

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TENNESSEE VALLEY AUTHORITY i

DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.20 License No. DPR-77 1.

The Nuclear Regulatory Commission (the Commission) has found that:

i 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 August 16, 1982, 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 Com-l 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 (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 conson

(

defense and security or to the health and safety of the public; and l

l 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, the license is hereby amended by page changes to the Appendix A Technical Specifications as indicated in the attachments to this license amend-ment and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:

(2) Technical Specifications l

l The Technical Specifications contained in Appendix A, as revised through Amendment No. 20, are hereby incorporated into the license.

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The licensee shall ~ operate the facility in accordance with the Technical Speciftcations.

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION.

lT Elinor G. Adensam. Chief Licensing Branch No. 4 Division of Licensing

Attachment:

Appendix A Technical Specification Changes Date of Issuance:

December 23, 1982

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ATTACHMENT TO LICENSE AMENOMENT N0.20 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET NO.'50-327 Replace the following pages of the /ppendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Anendment number and contain vertical lines indicating the area of change. -

Amended

? ale 3/4 6-20 3/4 8-16 3/4 4-23a

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~ TABLE 3.6-2 (Continued)

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CONTAINMENT ISOLATION VALVES I

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i VALVE NUMBER FUNCTION MAXIMUM ISOLATION TIME (Seconds)

C i'i A.

PHASE "A" ISOLATION (Cont.)

-4 32.

FCV-62-63 RCP Seals 10 33.

FCV-62-72 Letdown Line 10 34.

FCV-62-73 Letdown Line 10 35.

FCV-62-74 Letdown Line 10 36.

FCV-62-77 Letdown Line 20 l

37.

FCV-63-23 Accum to Hold Up Tank 10 38.

FCV-63-64 WDS N to Accum 10 2

39.

FCV-63-71 Accum to. Hold Up Tank 10 40.

FCV-63-84 Accum to Hold Up Tank 10 4

'41.

FCV-68-305 WDS N to PRT 10 R

42.

FCV-68-307 PRTt$GasAnalyzer 10 43.

FCV-68-308 PRT to Gas Analyzer.

10-T 44.

FCV-70-85 CCS from Excess Lt Dn Hx 10 Es 45.

FCV-70-143 CCS to Excess Lt Dn Hx 60 4

46.

FCV-77-9 RCDT Pump Disch

.10 47.

FCV-77-10 RCDT-Pump Disch 10 48.

FCV-77-16 RCDT to Gas Analyzer 10 49.

FCV-77-17 RCDT to Gas Analyzer 10 J,

50.

FCV-77-18 RCDT and PRT to V H 10 51.

FCV-77-19 RCDT and PRT to V H 10 52.

FCV-77-127 Floor Sump Pump Disch

'10 4

53.

FCV-77-128 Floor Sump Pump Disch 3 10*

54.

FCV-81-12 Primary Water Makeup

' 10

/#

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l 55.

FCV-87-7 UHI Test-Line 10, 56.

FCV-87-8 UHI Test Line 10 k

57.

FCV-87-9 UHI Test Line 10

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FCV-87-10 UHI Test Lina 10 59.

FCV-87-11

'UHI Test Line

' ~4 10 C

5 60.

FCV-26-240 Fire Protection Isol.

20

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20 2

61.

FCV-26-243 Fire Protection Isol.

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_ _ S REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM - WITHDRAWL SCHEDkJLE Q.

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CAPSULE VESSEL LEAD e

c NUMBER LOCA1 ION FACTOR WITH0RAWAL TIME (EFPY) z 8 REFUELING T

-40*

3.73 1

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140*

t 3.73 3

1 X

220*

3.73 5-Y 320*

3.73 9

5 4*

1.09 EOL V

176*

1.09 STBY R

W 184*

1.09 STBY t

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356*

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ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

(c) For each circuit breaker found inoperable during these functional tests, an additional representalve sample of at least 1 of the curcuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.

2.

By selecting and functionally testing a representative sample of at least 10% of each type of lower voltage circuit breakers.

Circuit breakers selected for functional testing shall be selected on a rotating basis.

The functional test shall consist of injecting a current input at the specified setpoint to each selected circuit breaker and verifying that each circuit breaker functions as designed.

Circuit breakers found inoperable during functional testing shall be restored to OPERABLE status prior to resuming operation.

For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 10% of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.

3.

By selecting and functionally testing a representative sample of e

each type of fuse on a rotating basis.

Each representative sample of fuses shall include at least 10% of all fuses of that type.

The functional test shall consist of a non-destrdctive resistance measure-ment test which demonstrates that the fuse meets its manufacturer's design criteria.

Fuses found inoperable during these functional tests shall be replaced with OPERABLE fuses prior to resuming operation.

For each fuse found inoperable during these functional tests, an additional representative sample of at least 10% of all fuses of that type shall be functionally tested until no more failures are found or all fuses of that type have been functionally tested.*

b.

At least once per 60 months by subjecting each circuit breaker to an inspection and preventive maintenance in accordance with procedures prepared in conjunction with its manufacturer's recommendations.

A fuse inspection and maintenance program will be maintained to ensure that:

1. The proper size and type of fuse is installed,
2. The fuse shows no sign of deterioration, and y.
3. The fuse connections are tight and clean.

SEQUOYA!! - UNIl 1 3/4 8-16 Amendment No. 20

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TENNESSEE VALLEY AUTHORITY 00CKEf NO. 50-328 SEQUOYAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE I

Amendment No.10 License No. OPR-79 I

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for mendment to the Sequoyah Nuclear Plant, Unit' 2 (the facility) Facility Operating License No. DPR-79 filed by the Tennessee Valley Authority (licensee), dated August 16, 1982, complies with the standards and requirments 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, i

the provisions of the Act, and the rules and regulations of the Com-i mission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and j

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 satisfied.

i 2.

Accordingly, the license is hereby amended by page changes to the Appendix A Technical Specifications as indicated in the attachments to this license mendment 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 Appendix A, as revised through Amendment No.14 are hereby incorporated into the license.

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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 b

Elinor G. Adensam Chief Licensing Branch No. 4 Division of Licensing Attactinent:

Appendix A Technical Specificetion Changes Date of Issuance: December 23, 1982 I

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ATTACHMENT TO LICENSE AMENDMENT NO. 10 FACILITY OPERATING LICENSE NO. DPR-19 DOCKET NO. 50-329 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

Amended Page 3/4 6-20 3/4 4-29 I

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TABLE 3.6-2 (Continued)

ME CONTAINMENT ISOLATION VALVES S!

3E VALVE NUMBER FUNCTION MAXIMUM ISOLATION TIME (Seconds) b A.

PHASE "A" ISOLATION (Cont.)

-d 32.

FCV-62-63 RCP Seals 10 33.

FCV-62-72 Letdown Line 10 34.

FCV-62-73 Letdown Line 10 35.

FCV-62-74 Letdown Line 10 36.

FCV-62-77 Letdown Line 20 I'

37.

FCV-63-23 Accum to Hold Up Tank 10 38.

FCV-63-64 WDS N to Accum 10 2

39.

FCV-63-71 Accum to Hold Up Tank 10 40.

FCV-63-84 Accum to Hold Up Tank 10 41.

FCV-68-305 WDS N, to PRT 10 42.

FCV-68-307 PRT tB Gas Analyzer 10 t'

43.

FCV-68-308 PRT to Gas Analyzer 10 i

44.

FCV-70-85 CCS from Excess Lt Dn Hx 10 i'

45.

FCV-70-143 CCS to Excess Lt Dn Hx 60 E!

46.

FCV-77-9 RCDT Pump Disch 10 47.

FCV-77-10 RCDT Pump Disch 10 4

48.

FCV-77-16 RCDT to Gas Analyzer 10 49.

FCV-77-17 RCDT to Gas' Analyzer 10 50.

FCV-77-18 RCDT and PRT to V H

-10 51.

FCV-77-19 RCDT and PRT to V H 10 j

52.

FCV-77-20 N to RCDT 10 53.

FCV-77-127 F$oorSumpPumpDisch 10 i

54.

FCV-77-128 Floor Sump Pump Disch 10 55.

FCV-81-12 Primary Water Makeup 10 g.

56.

FCV-87-7 UHI Test Line 10 R

57.

FCV-87 UHI Test Line 10 1

R 58.

FCV-87-9 UHI Test Line 10 5

59.

FCV-87-10 UHI Test Line 10 60.

FCV-87-11

.UHI Test Line 10 z

P 61.

FCV-26-240 Fire Protection Isol.

20 g

62.

FCV-26-243 Fire Protection Isol.

20 I.

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TABLE 4.4-5 E

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~ REACTOR VESSEL Mt.TERIAL SURVEILLANCE PROGRAM - WITHDRAWL SCHEDULE f

-<g 4

CAPSULE VESSEL LEAD g

NUMBER.

LOCATION FACTOR WITH0RAWAL TIME (EFPY) 8 REFUELING T

40' 3.73 1

U 140*

3.73 3

i X

220' 3.73 5-Y 320*

3.73 9

5 4'

1.09 EOL V

176*

1.09 STBY 4

s

[

W 184*

1.09 STBY D$

Z 356' 1.09 STBY e

4 F

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