ML20133K634

Proposed Change 130,revising Tech Spec Pages 51,109,110 & 124 to Delete Sections Requiring Valves in Equalizer Piping Be Closed During Reactor Operation

ML20133K634
Person / Time
Site:	Vermont Yankee
Issue date:	10/09/1985
From:	VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML20133K626	List: ML20133K623 ML20133K634
References
NUDOCS 8510220217
Download: ML20133K634 (4)

Text

_ _ . . _ _ ___ . _ . _ . . . _ . _ . _ _ _ _ _ _ _ _ - _ _ . . _ _ _ _ _ _ _ _ . _ - . .__ _ _ _ . _ _ _ . _ _ . _ _ . . _ _ .

VYNPS TABLE 4.2.1 (centinued)

Lcw Pressure Coolant Injection System Calibration (8) Instrument Check Trio Punction Punction Test (8)

(Ncte 1) Once/ Operating Cycle ---

Low Reactor Pressure #1 Once/Operatinr, Cycle Once Each Day High Drywell Pressure #1 (Note 1)

Once/ Operating Cycle Once Each Day Low-Low Reactor Yessel Water Level (Note 1)

(Note 1) Every 3 Months ---

Reactor Vessel Shroud Level (Note 1) Once/ Operating Cycle ---

Low Reactor Pressure #2 (Note 1) Every 3 Months ---

RHR Pump Discharge Pressure (Note 1) Every 3 Months --

High Drywell Pressure #2 (Note 1) Every 3 Months ---

Low Reactor Pressure #3 Every Refueling Outage Once Each Day Auxiliary Power Monitor (Note 1)

None Once Each Day Pump Bus Power Monitor (Note 1)

Every 6 Months Every 6 Months --

Trip System Logic (Note 3)

(Note 2) 51 Amendment No. 58, 76 8510220217 851009 PDR ADOCK 05000271 PDR P

't VYEPS 3.6 LIMITING CONDITION FOR OPERATION 4.6 SURVEILLANCE REQUIREMENT E. Structural Integrity E. Structural Integrity The structural intergrity of the primary The nondestructive inspections listed in system boundary shall be maintained at the Table 4.6.1 shall be performed per the level required by the original acceptance requirements of the 1974 edition of ASME, standards throughout the life of the plant. Section XI, up to and including the 1975 Sumer Addenda except piping examinations (Cat. F & J) shall be per the requirements of ASME Section KI, 1974 edition, 1976 Summer Addenda, Appendix III.

. F. Jet Pumps Recording levels shall be at 50% of the

1. Whenever the reactor is in the reference level, startup/ hot standby or run modes, all jet pumps shall be intact and all F. Jet Pumps operating jet pumps shall be operable.

If it is determined that a jet pump is 1. Whenever there is recirculation flow

!' inoperable, an orderly shutdown shall be with the reactor in the startup/ hot initiated and the reactor shall be in a standby or run modes, jet pump integrity l cold situation condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. and operability shall be checked daily by verifying that the following two

2. Flow indication from each of the twenty conditions do not occur simultaneously:

jet pumps shall be verified prior to a initiation of reactor strtup from a cold a. The recirculations pump flow shutdown condition. differs by more than 10% from the established speed-flow

3. The indicated core flow is the sum of characteristics.

I the flow indication from each of the twenty jet pumps. If flow indication b. The indicated total core flow is failure occurs for two or more jet more than 10% greater than the core pumps, imediate corrective action shall flow value derived from established be taken. If flow indication for all power--core flow relationship.

]

but one jet pump cannot be obtained within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> an orderly shutdown 2. Additionally, when operating with one shall be initiated and the reactor shall recirculation pump, the diffuser to lower be in a cold shutdown condition within plenum differential pressure shall be 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. checked daily, and the differential pressure of any jet pump in the idle loop shall not vary by more than 10%

from established patterns, j Amend: tent No. 45 109 2

(YNPS 3.6 LIMITING CONDITION FOR OPERATION 4.6 SURVEILLANCE REQUIREMENT

3. The baseline data required to evaluate the conditions in Specifications 4.6.F.1 and 4.6.F.2 '

G. Single Loop Operation shall be acquired each operating cycle.

1. Operation with a single recirculation loop is permitted for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless the recirculation loop is sooner made cperable.

If the loop cannot be made operable, the reactor shall be in cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

H. Recirculation System

1. This section deleted.

Amendment No. 29 110

A VYNPS 3.6 & 4.6 (cont'd)

The following factors form the basis for the surveillance requirements:

A break in a jet pump decreases the flow resistance characteristic of the external piping loop causing the recirculation pump to operate at a higher flow condition when compared to previous operation. ,

The change in flow rate of the failed jet pump produces a change in the indicated flow rate of that pump .

relative to the other pumps in that loop. Comparison of the data with a normal relationship or pattern provides the indication necessary to detect a failed jet pump.

The jet pump flow deviation pattern derived from the dif fuser to lower plenum differential pressure readings will be used to further evaluate jet pump operability in the event that the jet pumps fail the test in Specifications 4.6.F.1 and 2.

Agreement of indicated core flow with established power-core flow relationships provides the most assurance that recirculation flow is not bypassing the core through inactive or broken jet pumps. This bypass flow is reverse with respect to normal jet pump flow. The indicated total core flow is sumation of the flow indications for the twenty individual jet pumps. The total core flow measuring instrumentation suas reverse jet pump flow as though it were forwarded flow. Thus, the indicated flow is higher than actual core flow by at least twice the normal flow through any backflowing pump. Reactivity inventory is known to a high degree of confidence so that even if a jet pump failure occurred during a shutdown period, subsequent power ascension would promptly demonstrate abnormal control rod withdrawal for any power-flow operating map point.

A nozzle-riser system failure could also generate the coincident failure of a jet pump body; however, the converse is not true. The lack of any substantial stress in the jet pump body makes failure impossible without an initial nozzle-riser system failure.

G. Single Loop Operation An evaluation was not provided for ECCS performance during reactor operation with one recirculation loop out of service. Therefore, reactor operation for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> under such conditions will not be authorized until the necessary analyses have been performed, evaluated and deemed acceptable.

H. Recirculation System This section deleted.

Amendment No. 29 124 9

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