ML20011D498

Proposed Tech Specs Re Physical Location for Valve 2CV-5255-1 for Penetration 2P60 & Surveillance Requirements for End Anchorages & Adjacent Concrete Surfaces & Containment Surfaces

ML20011D498
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/15/1989
From:	ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20011D497	List: ML20011D496 ML20011D498
References
NUDOCS 8912270325
Download: ML20011D498 (8)

Text

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l ATTACHMENT PROPOSED TECHNICAL SPECIFICATION CHANGE LICENSE AMENDMENT REQUEST s IN THE MATTER OF AMENDING LICENSE NO NPF-6'--

' ARKANSAS POWER & LIGHT COMPANY ~

ARKANSAS NUCLEAR ONE., UNIT 2 o-DOCKET NO. 50-368=

DECEMBER 15,-1989 h-t

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Proposed Change No. 1 l

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This change maket certain administrative corrections to Table 3.6-1. First, i the physical location of valve 2CV-5255-1 for penetration 2P60 as noted in Table 3.6-1 is incorrect. The existing functional description is "CCW from RCP Coolers Isolation (inside)." The correct function should be "CCW from RCP Coolers Isolation (outside)." Second, for penetration 2P46 valves j 2IA-14 and 2IA-15 were renumbered as 2BA-217 and 2SA-216, respectively, as t result of a design change which also redesignated the piping from l "instrumerit air supply" to " breathing air supply." The design change involved disconnecting the instrument air line to the reactor building, reconnecting the reactor building instrument air line to the breathing air i system, and redesignating the affected valve and piping as a part of the

• breathing air system. The NRC.was advised of the relabelling of these valves in our letter of September 30, 1985 (2CAN998597).

Proposed Change No. 2 This change corrects an apparent typographical error in Specification 4.6.1.5.2, where reference to " Specification 4.6.1.6.1 "is incorrect since there is no such specification. The correct reference is

" Specification 4.6.1.5.1."

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DETERM1WATION OF SIGNIFICANT HAZARDS l

-i Arkansas Power & Light Company has performed an analysis of the proposed change in accordance with 10CFR90.91(a)(1) regarding no significant hazards consideration, using the standards in 10CFR90.92(c): l l

1) The proposed changes would not increase the probability or consequences of any accident previously evaluated since these editorial changes do not provide any relief from the requirements of the Technical Specifications, or change the intended operation or administrative requirements of the plant. .

2) The proposed changes would not create the possibility of a'new or different kind of accident from any previously analyzed since these editorial changes do not adversely-affect any coEponents or systems-which contribute to the safety of the plant or the' ability to properly handle potential offsite releases.

3) The proposed changes would not involve a significant reduction in the margin of safety since these editorial changes provide the correct valve designations and correct a typographical error but have no effect on any plant safety parameters or accident mitigation capabilities.

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The~ Commission has provided guidance concerning the application of these standards by providing examples. The proposed amendment is most closely encompassed by example (1): purely administrative 1y changes to-the Technical Specifications.

Therefore, based on the reasoning presented above and the previous discussion of the amendment request, AP&L has determined that the requested changes do not involve a sig- 1.; ant hazards consideration.-

h CONTAINMENT SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) 4.6.1.5.2 End Anchorages 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 surfaces shall be l demonstrated by determining through inspection that no apparent 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 rate tests (reference Specification 4.6.1.2) while the containment is at its maximum test pressure.

4.6.1.5.3 Containment Surfaces The structural integrity of the exposed accessible interior and exterior surf aces of the containment, including the liner plate, shall be determined during the shutdown for each Type A containment leakage rate test (reference Specification 4.6.1.2) by a visual inspection of these surf aces and verifying r.o apparent changes in appearance or other abnormal degradation.

4.6.1.5.4 Deleted ARKANSAS - UNIT 2 3/4 6-9 Amendment No. 91

TABLE 3.6-1 2 .

CONTAINMENT ISOLATION VALVES E

PENETRATION ISOLATION El . NUMBER VALVE NUMBER FUNCTION TIME (SEC) w m A. CONTAINMENT ISOLATION 2P7 2CV-5852-2# "A" S/G Sample Isolation (outside) 5 20 2CV-5859-2# "B" S/G Sample Isolation (outside) 5 20 2P8 2SV-5833-1 RCS & Pressurizer Sample Isolation (inside) 5 20 2SV-5843-2 RCS & Pressurizer Sample Isolation (outside) 5 20 2P9 2CV-6207-2 H.P. Nitrogen to SI Tanks (outside) 5 20 2P14 2CV-4821-1 CVCS L/D Isolation (inside) 5 35 2CV-4823-2 CVCS L/D Isolation (outside) $ 20 2P18 2CV-4846-1 RCP Seal Return Isolation (inside) 5 25 R:

2CV-4847-2 RCP Seal Return Isolation (outside) 5 20 2P31 2CV-2401-1 Containment Vent Header (inside) $ 20 3' 2CV-2400-2 Containment Vent Header (outside) 5 20 as 2P37 2SV-5878-1 Quench Tank Liquid Sample (inside) 5 20 2SV-5871-2 Quench Tann Liquid Sample (outside) 5 20 2SV-5876-2 SI Tanks Sample Isolation (outside) 5 20 2P39 2CV-4690-2 Quench Tank Makeup & Demin Water Supply Isolation (outside) 5 20 2P40 2CV-3200-2 Fire Water Isolation (outside) 5 20 2P41 2CV-6213-2 L.P. Nitrogen Supply Isolation (outside) 5 20 E 2P51 2CV-3852-1 Chilled Water Supply Isolation (outside) 5 20

.@ 2P52 2CV-5236-1 CCW to RCP Coolers Isolation (outside) 5 20

' S- 2P59 2CV-3850-2 Chilled Water Return Isolation (inside) 5 20

@' -2CV-3851-1 Chilled Water Return Isolation (outside) 5 20 2P60 2CV-5254-2 CCW from RCP Coolers Isolation (inside) 5 20 jf 2CV-5255-1 CCW from RCP Coolers Isolation (outside) 5 20 l

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TABLE 3.6-1 (Cont.) .

CONTAINMENT ISOLATION VALVES

$l PENETRATION ISOLATION NUMBER VALVE NUMBER FUNCTION TIME (SEC)

SE C. MANUAL

.-4 no 2P7 2CV-5850#* "A" S/G Sample Isolation (inside)r operated from 2C17 N.A.

2CV-5858#* "B" S/G Sample Isolation (inside), operated from 2C17 N.A.

2P19 2FP-35# Refueling Canal Recirculation Line (inside) N.A.

2FP-34 Refueling Canal Recirculation Line (outside) N.A.

2P32 2CV-1015#* "A" S/G Blowdown Isolation (inside),

operated from 2C33 N.A.

2P37 2SV-5872#* SI Tank 2T2A Sample (inside) N.A.

2SV-5873#* SJ Tank 2T2B Sample (inside) N.A.

Ri 2SV-5874#* SI Tank 2T2C Sample (inside) N.A.

• • 2SV-5875#* SI Tank 2TZD Sample (inside) N.A.

S' 2P42 2PH-44# Plant Heating Return Isolation (inside) N.A.

E! 2PH-45 Plant Heating Return Isolation (outside) N.A.

2P43 25A-68 Service Air Supply Isolation (outside) 2P46 28A-217 Breathing Air Supply Isolation (outside). l 2P48 2PH-22 Plant Heating Supply Isolation (outside) N.A.

2PH-23# Plant Heating Supply Isolation (inside) N.A.

2P64 2CV-1065#* "B" S/G Blowdown Isolation (inside),

operated from 2C33 N.A.

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TABLE 3.6-1 (Cont.) .

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CONTAINMENT ISOLATION VALVES

-$ PENETRATION ISOLATION 7 NUMBER VALVE NUMBER FUNCTION TIME (SEC)

E C. MANUAL (Cont.)

to 2C3 2CV-5432# Fuel Transfer Tube-Isolation (outside) N.A.

O. OTHER (Check Valves) 2P9 2N2 -18# H.P. Nitrogen to SI Tanks (inside) N.A.

2P39 2CVC-78# Quench Tank Makeup & Demin Water Supply (inside) N.A.

2P40 2FS-37# Fire Water Isolation (inside) N.A.

2P41 2N 2 -l# L.P. Nitrogen Supply Isolation (inside) N.A.

2P43 2SA-69 Service Air Supply Isolation (inside) N.A.

T 2P46 2BA-216 Breathing Air Supply Isolation (inside) N.A. l 2 PSI . 2AC-49# Chilled Water Supply Isolation (inside) N.A.

T 2PS2 2CCW-38# CCW to RCP Coolers Isolation (inside) N.A.

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1. Not subject to Type C leakage tests.

• May be opened on an intermittent basis under administrative control.

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