ML17156A729

Proposed Tech Specs,Extending Operation During Cycle 4 W/ One Recirculation Loop Out of Svc

ML17156A729
Person / Time
Site:	Susquehanna
Issue date:	08/10/1988
From:	PENNSYLVANIA POWER & LIGHT CO.
To:
Shared Package
ML17156A730	List: ML17156A729 ML17156A739 ML18040A910
References
NUDOCS 8808220133
Download: ML17156A729 (6)

Text

REACTOR COOLANT SYSTEH RECIRCULATION LOOPS - SINGLE LOOP OPERATION'-

LINITIHG COHOITIOH FOR OPERATION 3.4.1.1,2 One reactor. coolant recirculation loop shall be in operation with the pump speed < 80% of the rated puep speed, and

'a. the following revised specification lioits shall be followed:

l. Specification 2. 1.2: the HCPR Safety Liait shall be increased to 1. 07.

2. Table 2. 2.1-1: the APRH Flow. Biased Scraa Trip Setpoints shall be as follows:

Tri Se oint Al 1owabl e Value

3. Specification 3.2. I: The HAPLHGR lisits shall be by 0.8+~

~ ultiplied by 4-.9. ), g

4. Specification 3.2.2: the AplN Setpoints shall be as follows:

Tri Set oint Al 1owabl e Value 1 + 55K)T l us,eRT SRB

< (0.58W + 46X)T S~ < (O.SSI + 4%)T Table 3. 3. 6-2: the RBM/APN Control Rod Block Setpoints shall be as fo1 1 ows:

a. RBN - Upscale Tri Set oint Allowable Value

~ +

b, APRH-Flow Biased Tri Se oint Al 1 owabl e Value

~ +

b. APRN and LPGA%'">> neutron flux noise levels'hall be less than three tiaes their established baseline levels when THElNAL PtNER is greater than the liait specified in Figure 3/4.1.1.1-1.

c. Total core flow shall be greater than or equal to 42 aillion lbs/hr when THERNL REER is greater than the li it

~ specified in Figure 3.4.1.1.1-1.

'APPLICABILITY: OPERATIONAL CONOITIONS 1>> and 2>>, except during two loop operation. f SUSQUEHANNA

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3/4. 4 REACTOR COOLAHT SYSTEH BaSES 3/4.4. 1 RECIRCULATIOH 'SYSTEH Operation with one reactor recirculation loop inoperable has been evaluated and found acceptable, provided that the unit is operated in accordance with Specification 3.4.1.1.2.

For .single loop operation, the RBM and APRM setpoints are adjusted by a 7X decrease in recirculation drive flow to account for the active loop drive flow that bypasses the core and goes up through the inactive loop jet pumps.

Surveillance on the pump speed of the operating recirculation loop is imposed to exclude the possibility of excessive reactor vessel internals vibr a-tion. Surveillance on differential temperatures below the threshold limits on THERHAL POWER or recirculation loop flow mitigates undue thermal stress on vessel nozzles, recirculation pumps and the vessel bottom head during extended operation in the single loop mode. The threshold limits are those values which wi ll sweep up the cold ~ater from the vessel bottom head.

THERHAL POWER, core flow, and neutron flux noise level limitations are pre-scribed in accordance with the recoenendations of General Electric Service Information Letter Ho. 380, Revision 1, "BWR Core Thermal Hydraulic Stability,"

dated February 10, 1984.

An inoperable jet poop is not, in itself, a sufficient reason to declare a recirculation loop inoperable, but it does, in case of a design-basis-accident, increase the blowdown area and reduce the capability of reflooding the core; thus, the requirement for shutdown of the facility with a jet pump inoperable.

Jet pump failure can be detected by monitoring jet pump performance on a prescribed schedule for significant degradation, Recirculation pump speed mismatch limits are in compliance with the ECCS LOCA analysis design criteria for two loop operation. The limits will ensu~e an adequate core flow coastdown from either recirculation loop following a LOCA.

In the case where the mismatch limits cannot be maintained during the loop operation, continued operation is permitted in the single loop code.

In order to prevent undue stress on the vessel nozzles and bottom head region, the recirculation loop temperatures shall be within 50 F of each other rior to star tup of an idle loop. The loop temperature must also be within 0 F of the reactor pressure vessel coolant temperature to prevent thermal shock to the recirculation p~ and recirculation nozzles. Since the coolant in the bottom of the vessel is at a lower temperature than the coolant in the upper regions of the core, undue stress on the vessel would result if the tem-perature difference was greater than 145'F.

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