ML20129H582

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Proposed Tech Spec Table 3.6-2,Page 3/4 6-26,deleting Isolation Valve NI-122B from List of Containment Isolation Valves.Valve Determined to Not Require Containment Isolation Signal.Util Determination Encl
ML20129H582
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
Issue date: 07/15/1985
From:
DUKE POWER CO.
To:
Shared Package
ML20129H566 List:
References
NUDOCS 8507190251
Download: ML20129H582 (6)
v • d • e


Text

7 TABLE 3.6-2 (Centinued) h CONTAINMENT ISOLATION VALVES a

A MAXIMUM h

VALVE NUMBER FUNCTION TIME (SEC)

ISOLATION ag 1.

Phase "A" Isolation (continued)

NI-96B Test HDR Outside Containment Isolation 110 g

NI-120B Safety Injection Pump to Accumulator Fill Line Isolation

$10 l

NI-255B UHI Check Valve Test Line Isolation 110 y

NI-258A UHI Check Valve Test Line Isolation

<10 NI-264B UHI Check Valve Test Line Isolation 710 NI-266A UHI Check Valve Test Line Isolation 710 NI-267A UHI Check Valve Test Line Isolation 710 NM-3A Pressurizer Liquid Sample Line Inside Containment Isolation 115 mg NM-6A Pressurizer Steam Sample Line Inside Containment Isolation

$15 3"

NM-78 Pressurizer Sample Header Outside Containment Isolation

$15 g

NM-22A NC Hot Leg #1 Sample Line Inside Containment Isolation

<15 i

i5 '$$

NM-25A NC Hot Leg #4 Sample Line Inside Containment Isolation 515 2c NM-26B fic Hot Legs Sample Hdr. Outside Containment Isolation

<l5 d

NM-728 NI Accumulator A Sample Line Inside Containment Isolation 215

~

M NM-75B NI Accumulator B Sample Line Inside Containment Isolation 515 fu f;M-788 NI Accumulator C Sample Line Inside Containment Isolation

<15 d

NM-81B NI Accumulator D Sample Line Inside Containment Isolation 515 NM-82A NI Accumulator Sample Hdr. Outside Containment Isolation

$15 om uu NM-187A#

SG A Upper Shell Sample Containment Isolation Inside

<15

@80 NM-190A#

SG A Blowdown Line Sample Containment Isolation Inside 715 Og f4M-191B#

SG A Sample Hdr. Containment Isolation Outside 515 2 0-HM-1978#

SG B Upper Shell Sample Containment Isolation Inside

<15 fiM-200B#

SG B Blowdown Line Sample Containment Isolation Inside 515 NM-201A#

SG B Sample Hdr. Containment Isolation Inside

$15 f4M-207A#

SG C Upper Shell Sample Containment Isolation Inside

$15 NM-210A#

SG C Blowdown Line Sample Containment Isolation Inside

$15 f4M-2118#

SG C Sample Hdr. Containment Isolation Outside 115 NM-217B#

SG D Upper Shell Sample Containment Isolation Inside 115 NM-220B#

SG D Blowdown Line Sample Containment Isolation Inside

<15

p Attachment II Justification and Safety Analysis This proposed change concerns the deletion of isolation valve NI-122B from Tabic 3.6-2 of the McGuire Technical Specifications. At present this valve is subject to operability requirements (T.S. 3.6.3) and surveillance requirements (T.S. 4.6.3).

Technical Speelfication 3.6.3 requires that valves listed in Table 3.6-2 be operable with isolation times which are specified in Table 3.6-2.

Duke Power Company has determined that valves 1NI-122B and 2NI-122B do not require a containment isolation signal (S ) and therefore should be deleted T

from Table 3.6-2.

The containment isolation systems are designed to provide the means of isolating fluid systems that pass through penetrations so as to prevent leakage of radioactivity from the containment following a design basis accident.

Valve NI-122B is located on a 3/4" line which branches off the 4" Nuclear Safety Injection System (NI) lines as shown in Figures 1 and 2.

The 4" NI lines provide safety injection flow to the Reactor Coolant System hot legs, and would be under high pressure following an accident. NI-122B is in a Safety Injection System check valve test header line. This valve is normally closed and would be open only during a plant shutdown. Present administrative controls require verification of all NI valve positions prior to unit startup.

If NI-122B was open in an accident situation, the high pressure in the 4"-NI lines would prevent leakage of radioactivity from the containment to the auxiliary building.

Since valve NI-122B does not require an isolation signal (ST). a station modification would eliminate the automatic closure feature for valve NI-122B.

The signal is not required for valve NI-122B as it is normally closed during plant operation and controlled administratively. The modification to remove the containment isolation signal (S ) from valves 1NI-122B (Unit 1) and T

2NI-122B (Unit 2) will be initiated upon NRC granting the proposed amendment of the Technical Specifications. The proposed changes would eliminate unnecessary surveillance and testing on valves NI-122B and reduce time in Containment thereby reducing personnel exposure.

r Attachment III Analysis of Significant Hazards Consideration Pursuant to the requirements of 10CFR50.91, the following analysis provides a determination that the proposed changes of the Technical Specifications, Table 3.6-2 do not include any significant hazards consideration, as defined by 10CFR50.92.

The Technical Specification change to delete valve NI-122B from the Table 3.6-2,and the modification to remove the containment isolation signal (S_)

from NI-122B, is being proposed as this valve does not require a contain$ent isolation signal (S ).

Valve NI-122B is normally closed during operation T

isolation signal (S ) to a valve normally and removal of containment T

closed during operation does not adversely affect safety. At other times the valve line is full of high pressure safety injection water and would not provide a path for radioactivity releases.

The opening and closing of the valve is administratively controlled.

The inclusion of an ST signal on this valve was inadvertent.

The proposed amendments would not:

1)

Involve a significant increase in the probability or consequences of an accident previously evaluated; or

2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or 3)

Involve a significant reduction in a margin of safety.

Based upon the preceding analy>!ts, Duke Power Company concludes that the proposed amendments do not involve a significant hazards consideration.

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