ML20248D492

Proposed Tech Specs,Revising Schedule for Surveillance Requirements (Srs) 4.3.3.7.20.b,4.7.11.2.c.2,4.7.11.2.c.3, 4.7.11.4.b.2 & 4.7.11.4.b.3 to Defer Performance of SRs Until 891215

ML20248D492
Person / Time
Site:	Sequoyah
Issue date:	09/29/1989
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20248D487	List: ML20248D482 ML20248D492
References
NUDOCS 8910040291
Download: ML20248D492 (9)

Text

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ENCLOSURE 1.

PROPOSED TECHNICAL-SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNIT 1 DOCKET NO. 50-327-(TVA-SQN-TS-89-l42)-

LIST OF AFFECTED PAGES Unit 1 3/4 3-57a 3/4 7-34 3/4 7-37 1

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j PLANT SYSTEMS -

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SURVEILLANCE REQUIREMENTS (Continued)

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c. At least once per 18 months:  ;

1. By performing a system functional test which includes simulated i automatic actuation of the system, and: -

a) Verifying that the automatic valves in the flow path-actuate to their correct positions on a cross zone or single zone detection test signal as designed, and b). Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel.

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2. By visual inspection of the dry pipe, spray and sprinkler headers to verify their integrity, and *

3. By visual inspection of each nozzle's spray 'area to verify the spray pattern is not obstructed. A

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MAR 251982 SEQUOYAH - UNIT 1 3/4 7-34 Amendment No. 12 . R16. .,

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PLANT SYSTEMS FIRE H0SE STATIONS

i. M MITING CONDITION FOR OPERATION

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3.7.11.4 The fire hose stations shown in Tabl.e 3.7-5 shall be OPERABLE. R118

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E APPLICABILITY

Whenever equipment in the' areas protected by the fire hose .,'

stations is required to be OPERABLE. i. .

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ACTION: d -

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a. With one or more of the fire hose stations shown in Table 3.7 All8 inoperable, route an additional equivalent capacity fire hose to the '

unprotected area (s) from an OPERABLE hose station within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if

'the inoperable fire hose is the primary means of fire suppression; .'

. otherwise route the additional bose within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Restore the .

, fire hose station to OPERABLE status within 14 days or, in lieu of t any other report required by Specification 6.6.1, prepara and submit a Special Report to the Commission pursuant to Specification 6.9.2 -

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. within the next 30 days outlining the action taken, the cause of the inopera'bility, and the plans and schedule for s testoring the station i

• to OPERABLE status. -

b. The provisions of Specifications 3.0.3 and 3.0.4 are not' applicable.

. SURVEILLANCE REQUIREMENTS 5'

4.7.11.4 Each of the fire hose stations shown in Table 3.7-10 shall be .. ,

L demonstrated OPERABLE:

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" At least o'nce per 31 days by visual inspection of the stations ' ". .

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accessible during plant operations to assure all. required equipment 2 is at the station.

b. At least once per 18 months by:

.c Visualinspectionoftheitationsnotaccessibleduringplant 1.

operations to assure all required equipment is at the station, '

2. Removing the hose for inspection and re-racking, and

3. Inspecting all gaskets and r,eplacing any degraded gaskets in the couplings.* -

c. At least once per 3 years by:

1. Partially opening each hose station valve to verify valve <

__ OPERABILITY and no flow blockage. -

2. Conducting a hose hydrostatic test at a pressure of 150 psig or l

, at least 50 psig above maximum fire main operating pressure,  ;

I whichever is greater. . ,

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• M N D E M SEQUOYAH - UNIT 1 3/4 7-37 OM. . .

Amendment No.~36, 114

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3 ENCLOSURE 2

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' PROPOSED TECHNICAL SPECIFICATION CHANGE l e SEQUOYAH NUCLEAR PLANT UNIT 1  !

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DOCKET NO. 50-327

l (TVA-SQN-TS-89-42) l DESCRIPTION AND JUSTIFICATION FOR .I SCHEDULE CHANGE TO SURVEILLANCE REQUIREMENTS' j 4.3.3.7.20.b, 4.7.11.2.c.2, 4.7 11.2.c.3,

.4.7.ll.4.b.2, and 4.7.11.4.b.3 l

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. ENCLOSURE 2 Description of Change

' Tennessee Valley Authority proposes to modify the_Sequoyah Nuclear Plant g, (SON) Unit.1. technical specifications (TSs) to revise the schedule for surveillance requirements (SRs) 4.3.3.7.20.b,_4.7.ll.2.c.2, 4.7.11.2.c.3,

'4.'7.11.4.b.2, and 4.7.11.4.b.3 to defer the performance of these SRs until December 15, 1989.

Reason for Change These TS changes are required to allow continued operation of Unit 1 until the ne ;t planned outage, which is scheduled to begin the first week in December 1989. Access to the area inside the polar crane W511 (required to perform the subject S..s) is prohibited during power operation because of high radiation levels.

justification for Change Failure to perform SR 4.3.3.7.20.b will result in the high-range containment area. lower compartment radiation monitors being. declared technically inoperable._ TS 3.3.3.7 requires a minimum of one channel to be operable' while. the unit is in Modes 1, 2, or 3. The system installed at SQN consists of two redundant channels of high-range monitors (RM-90-273 and RM-90-274) in the lower compartment. It is not expected that both of these channels would fall to perform their intended function during the period of time requested by this change (approximately seven weeks). Additier.9 assurance that the lower compartment monitors would continue to perform their intended function is provided by performance of a monthly CHANNEL CHECK required by TS 3.3.3.7. In the unlikely event that both of the lower compartment high-range radiation monitors were to fail, an alternate method of monitoring this parameter exists through use of the postaccident sampling system.

Failure to perform the visual inspections required by SRs 4.7.11.2.c.2 and 4.7.11.2.c.3 in the area of the reactor coolant pumps (RCPs) would require the subject equipment (spray and/or sprinkler systems) to be declared inoperable. The spray and/or sprinkler systems in the area of the RCPs are passive systems; therefore, failure to visually inspect the subject portions of the systems would not prevent the system from performing its intended function in the event of a fire in the area of an RCP.

Failure to perform SRs 4.7.11.4.b.2 and 4.7.11.4.b.3 for the fire houe stations located inside the polar crane wall would require the subject equipment (fire hose stations) to be declared inoperable. The fire hoses inside tN polar crane wall are inaccessible during power operation and, therefore, should not have been tampered with or removed since the last performance of the SR. Condition of the hoses (i.e., couplings, gasket material, etc.) is not expected to be adversely affected by the requested extension to the surveillance interval.

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.. As described above, access to the area inside the polar crane wall (required to perform the subject SRs) is prohibited during power operation because of high radiation levels. Extension'of the required surveillance interval for the subject SRs until December 15, 1989, (approximately seven weeks) will not prevent the subject equipment from performing its intended functions. Therefore, TVA submits that granting of the requested changes does not negate the underlying purpose of the TSs.

Environmental Impact Evaluation The. proposed change request does not involve an unreviewed environmental question because operation of SQN Unit 1 in accordance with this change would not:

1. Result in a significant increase in any adverse environmental impact previously evaluated in the Final Environmental Statement (FES) as modified by the Staff's testimony to the Atomic Safety and Licensing Board, supplements to the FES, environmental impact appraisals, or in any decisions of the Atomic Safety and Licensing Board.

2. Result in a significant change in effluents or power levels.

3. Result in matters not previously reviewed in the licensing basis for SQN that may have a significant environmental impact.

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. L ENCLOSURE 3 l

PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNIT 1 DOCKET NO. 50-327 (TVA-SQN-TS-89-42)

DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATIONS d

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"" . ENCLOSURE 3 Significant Hazards Evaluation

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.TVA has evaluated the proposed TS change and has determined that it does not represent a significant hazards consideration based on criteria established in 10 CFR 50.92(c). Operation of SQN in accordance with the <

proposed amendment will not: 1 (1) Involve a significant increase in the probability or consequences of 1 an accident previously evaluated.

The lower compartment high-range radiation monitors provide no .

automatic actuations. They are used only to provide information to the operator concerning the condition of the environment inside containment. In the event.that both channels of the lower compartment high-range radiation monitors fail, an alternate method of monitoring radiation levels in the lower compartment is available through use of the postaccident sampling system. The portions of the spray and/or sprinkler systems located in the area of the RCPs, as well as the hose stations inside the polar crane wall, do not perform any automatic actuation functions. This equipment is located in the area that is inaccessible during power operation and, therefore, should not have been altered since the last performance of the subject SRs. Extension of the surveillance interval for the subject SRs does not significantly increase the probability or consequences of an' accident previously evaluated.

(2) Create the possibility of a new or different kind of accident from any previously analyzed.

The subject SRs are performed on equipment that does not perform any automatic actuation functions and is not required to initiate any subsequent safety actuations. The lower compartment high-range radiation monitors provide only monitoring capabilities; the spray and/or sprinkler systems are passive components, and the hose stations are manually operated. Therefore, the proposed change, to extend the required surveillance interval approximately seven weeks, does not create the possibility of a new or different kind of accident from any previously analyzed.

(3) Involve a significant reduction in a margin of safety.

The subject SRs are performed on equipment that does not perform any automatic actuation functions and is not required to initiate any subsequent safety actuations. The lower compartment high-range radiation monitors provide only monitoring capabilities; the spray and/or sprinkler systems are passive components, and the hose stations are manually operated. Therefore, the proposed change does not cause a reduction in any margin of safety.

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