ML20055G931

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Amend 108 to License NPF-6,revising Tech Specs Table 3.6-1, Including Correction Indicating Location of Containment Isolation Valve & Relabelling of Two Other Containment Isolation Valves to Reflect Design Change
ML20055G931
Person / Time
Site: Arkansas Nuclear 
Issue date: 07/18/1990
From: Dudley R
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20055G932 List:
References
NPF-6-A-108 NUDOCS 9007240367
Download: ML20055G931 (10)


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UNITED $TATEs r?

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q NUCLEAR RE@ULATORY COMMISSION 5

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ENTERGY OPERATIONS. INC.

DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE. UNIT k AMENDMENT TO FACILITY OPERAT!NG LICENLJ Amendment n. 108 License No. NPF.

  • he Nuclear Regulatory Commission (the Comission) has found that:

1.

T A.

The application for amendment by Arkansas Power and Light Company-dated December 15,1989, complies with the standards and requirements of the Atomic Energy Act of 1954, an amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter !g The facility will operate in conformity with the application, ions B.

as amended, the provisions of the Act, and the rules and regulat of the Comission; C.

There is reasonable assurance:

(1)thattheactivitiesauthorized 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 license amendment will not be inimical to the comon d9fer.se 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 applicat,le requirements have been satisfied, hbk bi hh 66 P

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2.

Accordingly, the license is amended by changes to the Technical

$pecifications as indicated in the attachment to this license amendment,andParagraph2.C.(2)ofFacilityOperatingLicenseNo.

NPF-6 is hereby amended to reart as follows:

2.

TechnicalSpecifications 1

The Tocht,1 cal Specifications contained in Ap endix A, as revised through Amendment No.108, are hereb incorporated

. in the license. The licensee shall operate the facility in

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accordance with the Technical Specifications.

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The license amendsent is effective 30-days from the date of issuance, j

FOR THE NUCLEAR REGULATORY COP 9ti$$10N' l

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.i Richard F. Dudley, Acting or Project Directorate IV-1 i

Division of Reactor Projects - Ill, IV, Y and Special Projects i

Office of Nuclear Reactor Regulation'

Attachment:

Changes to the Technical Specifications l

Date of Issuance: July 18,1990 i

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ATTACHMENT TO Ljc_ENSE AMENON{NT_ NO.108 FACILITY OPERATING __ LICENSE NO. NPF.6 DOCKET NO. 50-366 Revise the following pages of the Appendix "A' Technical Specifications with the atteched pages. The revised pages are identified by Amendment number and contaia vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.

REMOVEPApES INSERT PAGES i

3/4 6-9 3/4 6-9 3/4 6-18 3/4 6-18 l

3/4 6 20 3/4 6-20 3/4 6-21 3/4 6-21 l

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CONTAINMENT SYSTEMS SURVEILLANCE kEDUIREMENTS (continuedi j

4.6.1.5.2 End Anchoranes and Adjacent Concrete Surfaces The structural integrity of the end anchorages of all tendons inspected pursuant to Specification 4.6.1.5.1 and the adjacent concrete surfacts shall be l

i demonstrated by determining through inspection that no appe. cent changes have occurred in the. visual appearance of the end anchorage or the concrete crack patterns adjacent to the end anchorages.

Inspections of the concrete shall be performed during the Type A containment leakage r&te tests (reference Specification 4.6.1.2) while the containment is at its maximum test pressure.

4.6.1.5/3 Containment surfacos The structural integrity of the exposed accessible interior and exter'or surfaces of the containment, including the liner plate, shall be deteraired during the shutdown for each Type A containment leakage rate test (reference Specification 4.6.1.2) by a visual ins'pection of these surfaces and verifying no apparent changes in appearance or other abnormal degradation.

i 4.6.1.5.4 Deleted l

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I l-l' ARKANSAS - UNIT 2 3/4 6-9 Amendment No. 52, 108

CONTA!NMENT.$YSTEMS

$URVE!LLANCE REQUIREMENTS (Continued) 4. 6. 3.1. 2 E'ach isolation valve specified in Table 3.6-1 shall be demonstrated OPERABLE during the COLD SHtTTDOWN or REFUELING MODE at least once per 18 months by verifying that on a containment isolation test signal, each isolation valve actuates tc its isolation position.

4.6.3.1.3 The isolation time of each power operated or sutomatic valve of Table 3.6-1 shall be determined to be within its limit when tested pursua,nt to specification 4.0.5.

4. 6. 3.1. 4 Prior to exceeding conditions which require establishment of f.eactor building integrity per TS 3.6.1.1, the leak rate of the contain-n.ent purge supply and exhaust isolation valves listed in Table 3.6,1 Part 8 shall be verified.to be within acceptable limits per TS 4.6.1.2. unless the test has been successfully completed within the last three months, b

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ARKANSAS-UNIT 2 3/4 6-17 Amendment Ilo.40 L

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TABLE 7.6-1 CONTAIISENT ISOLi. TION VALVES.

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PENETRATION ISOLATION'

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NUIRER V#.LVE IRNWER FUNCTION TIME (SEC) j

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~A.

CONTAIISENT ISOLATIOR l

2P7 2CV-5652-N "A" 5/G Sample Isolation (outside) 5 29 2CV-5859-28 "8" 5/G Sample Isolation (outside) 5 29 1

2P8 25V-5833-1 1105 & Pressurizer Sample Isolation (inside) 5 29-l 2SV-5843-2 NCS & Pressurizer Sasyle Isolatten (outside) 5 29 2P9 2CV-6207-2 N.P. MittwWen to SI Tanks ( M side) 5.20 l

2P14 2CV-4821-1 CVCS L/D Isolatten (Inside) 5 35 2CV-4823-2 CVCS L/D Isolation (outside) 5 29 2P18 2CV-4846-1 IICP Seal. Return Isolation (Inside) 5 25 Y

2CV-4847-2 RCP Seal Return Isolation (outside) 5 29 2P31 2CV-2491-1 Containment Vent Needer (inside) 5 29 l

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2CV-2499-2 Containment Vent Needer (outside) 5 29 I

5 2P37 25V-5878-1 Quench Tank Liquid Sample (Inside) 5 29 2SV-5871-2 quench Tank a.iguid Sample (outside) 5 29 i

2SV-5875-2 SI-Tanks Sample Isolatten (outside) 5 20 2P39 2CV-4699-2 Quench Tank Meheup & Desin Water Supply Isolation (outside) 5 20 2P49 2CV-3299-2 Fire Water Isolatten (outside) 5 29 2P41 2CV-6213-2 L.P. Nitrogen Sepply Isolation (outside) 5 29

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2P51 2CV-3852-1 Chilled Water Supply Isolation (outside) 5 20

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2P52 2CV-5236-1 CCW to RCP Coolers Isolatten (ettside)-

5 29 g

2PS9 2CV-3050-2 CA111ed Water Return Isoletten (inside) 5 29 i

a 2CV-3851-1 Chilled Water Return Isolatten (outside) 5 29-2P60 2CV-5254-2 CCW from RCP Coolers Isoletten (inside) 5 29 f

2CV-5255-1 CCW from RCP Coolers Isoletten (outside) 5 20 I

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TABLE 3.6-1 (Cont.)

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t CONTAllMENT ISOLATION VALVES

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W PENETRATION IS0t* TION NUNBER VALVE NUNBEN FUNCTION TIME (SEC) l Z

A. CONTAllMENT ISOLATION (Cont.)

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2F68 2CV-2060-1 Containment Sump Drain Isolation (inside)

< 20 2CV-2061-2 Containment Sump Drain Isolation (outside) 7 20 2P69 2CV-2202-1 Reactor Drain Tank Discharge (inside) i 20 1

2CV-2201-2 Reactor Drain Tank Discharge (outside) 1 20' B. CONTAllMENT PURGE 2P6 -

2SV-8231-2 Purge Inlet Isolation (outside)

< 20 I

i 2SV-8273-1 Purge Outlet Isolation (inside) 1 20 2SV-8271-2 Purge Outlet Isolation (outside)

< 20

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2P58 2SV-8261-2 ainment Atmosphere Sample (outside) i 20 2SV-8265-1 Containment' Atmosphere Sample (inside) 1 20 L

2SV-8263-2 Containment Atmosphere Sample (outside) 1 20 t

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2VI 2CV-8289-1 Contaisement Purge Inlet Isolation (inside)-

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2CV-8284-2 Contaisement Purge Inlet Isoiation (outside) 15'

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l 2CV-8283-1 Contaisement Purge Inlet Isolation (outside)

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2V2 2CV-8291-1 Containment Purge Outlet Isolation (inside) i5 l

l 2CV-8286-2 Contaisument Purge Outlet Isolation (outside)-

1 5 2CV-8285-1 Contaisement Purge Outlet Isolation (outside)

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TABLE 3.6-1 (Cent.)

S.

CONTAIIDENT ISOLATION VALVES.

ISOLATION

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5 PEETRATION

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y MtsEER VALVE IR98ER FINICTION TIE (SLQ E

C.

fWWIGAL 2P7 2CV-5850f*

"A" SM Sample Isoletien' (las1de), operated from 2C17 N.A.

2CV-5850f*

"B" SM Sample Isolatien (fas1de), opersted i

fren 2C17 N.A.

I 2P19 2FP-358 Refueling Canal Recirculation Line (inside)-

N.A.

'l 2FP-34 Refuel 1og Canal Rec 1rculatien Line (outside)

N.A.

2P32 2CV-1915#*

"A" SM Blowdsun Isolatten (faside),

eperated frees 2C33 N.A.

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2P37 25V-58728*

51 Tank 2T2A Sample (faside)

N.A.

i 25V-5873f*

SI Tank 2T2B Sample (fas1de)

N.A.

t R

25V-5874f*

SI Tank 2T2C Sample (faside)

N.A.

25V-587589 SI Tank 2T29 Sample (faside)

N.A.

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T 2P42 2PN-448 Plant IIeeting Return Isolatien (faside)

N.A.

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2PN-45 Plant Meeting Return Isoletten (outside)-

N.A.

1 2P43 254-68 Service A1r Sepply Isolatien (outside) 2P46 294-217 Breathing Air Segyly Isoletten (outside).

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H.A.

2P48 2PN-22 Plant Nesting Supply Isolatien (outs 1de) _

N.A.

2PN-238 Plant Neeting Supply Isolet1en (faside)-

2P64 2CV-1665#*

"B" SM Bleudoun Isolatten (Inside),

t sperated from 2C33 N.A.

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TABLE 3.5-1 (Cont.)

CONTAIOSENT ISOLATION VALVES, ISOLATION-E PENETRATION NtBIBER VALVE NUISER FINICTION TIfE (SEC)--

E C. peultat (Cont.)

4 Feel Transfer Tube Isolation (outside)

N.A.

m 2C3 2CV-54329 D. OTNER (Check Valves) 2P9 2Na-188 N.P. Mitrogen to SI Tanks (inside)

N.A.

2P39 2CVC-788 quench lank Meheap & Domin Water N.A.

Supply (inside) 2P40 2FS-378 Fire Water Isolatten (inside)

N.A.

2P41 2Na-18 L.P. Nitrogen Supply Isolation (inside)

N.A.

2P43 25A-69 Service Air Sepply Isoletten (inside)

N.A.

R 2P46 29A-216 Breathing Air Supply Isolation (faside)

N.A.

.l 2 PSI 2AC-498 Chilied Water Supply Isolatten (faside)

N.A.

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2PS2 2CCW-388 CCW to RCP Coolers Isolation (faside)

N.A.

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  1. Not subject to Type C leeko0e tests.

"May be opened on an intensittent basis under administrative control.

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CONTAINMENT SYSTEMS B

3/4.6;4 COMBUSTIBLE GAS CONTROL NYDROGEN ANALYZERS LIMITING _ CONDITION FOR OPERATION 3.6.4.1 Two independent containment hydrogen analyzers shall be OPERABLE.

I APPLICABILITY: MODES 1 and 2.

ACTION:

l With one hydrogen analyzer inoperable, restore the inoperable analyzer to OPERABLE status within 30 days or be in at least NOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

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SURVEILLANCE REQUIREMENTS 4.6.4.1 Each hydrogen analyzer shall be demonstrated OPERABLE at least once per 92 days on a STAGGERED TEST BASIS by performing a CHANNEL CALIBRATION using sample gases containing:

a.

Zero volume percent hydrogen, balance nitrogen, and b.

f'our volume percent (nominal) hydrogen, balance nitrogen.

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l ARKANSAS-UNIT 2 3/4 6-22