ML17158A045

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Safety Evaluation Supporting Amend 131 to License NPF-14
ML17158A045
Person / Time
Site: Susquehanna 
Issue date: 12/10/1993
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML17158A044 List:
References
NUDOCS 9312170127
Download: ML17158A045 (4)


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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR R GULATION RELATED TO AMENDMENT N0.131TO FACILITY OPERATING LICENSE NO.

NPF-14 PENNSYLVANIA POWER AND LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.

SUS UEHANNA STEAM ELECTRIC STATION UNIT 1

DOCKET NO. 50-354 1,0 INTRODUCTION By letter dated July 21,

1993, the Pennsylvania Power and Light Company (the licensee) submitted a request for changes to the Susquehanna Steam Electric
Station, Unit 1, Technical Specifications (TS).

The requested changes would modify the requirement for acquisition of baseline data on single-loop operation (SLO) from during startup testing following each refueling outage to at least once per 18 months.

This revision to the Unit 1 TSs is the same as the revision that the Commission approved for Unit 2 by Amendment No.

91 to License No.

NPF-22 on October 28, 1992.

2.0 EVALUATION The current TS for Susquehanna, Units 1 and 2, permit plant operation with a single recirculation loop out of service for an extended period of time.

However, there are a number of additional requirements when the plant is operated with only one rather, than two recirculation loops, such as the requirement to increase the minimum critical power ratio (MCPR) by 0.01 when in SLO.

One of the additional requirements specified in Surveillance Requirement (SR) 4.4. 1. 1.2.6 is that the operators have to demonstrate at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> that all jet pumps, including those in the inoperable

loop, are operable during SLO.

This is accomplished by comparing parameters such as total core flow with established baseline values.

The SR verifies jet pump integrity to assure the core could be flooded to two-thirds core height if the postulated design basis loss-of-coolant accident were to occur.

A footnote to SR 4.4. l. 1.2.6 now specifies that:

"During startup testing following each refueling outage, data shall be recorded for the parameters listed to provide a basis for establishing the specified relationships.

Comparisons of the actual data in accordance with the criteria listed shall commence upon the performance of subsequent required surveillances."

The licensee proposes to substitute the words:

"At least once per 18 months (555 days)" in place of "During startup testing following each refueling 9312170127 931210 PDR 'DDCK 05000387 P

PDR

outage" and to delete "subsequent" in the second sentence.

The changes to the TSs will permit the baseline data to be taken when SLO is scheduled for maintenance reasons rather than entering SLO for no reason other than to take data.

The proposed revised testing schedule would eliminate unnecessary plant cycling while taking advantage of SLO which is typically scheduled two or three times per fuel cycle for maintenance reasons.

Since the plant must be placed in SLO at low core flow to obtain the baseline

data, the revised testing schedule would likely eliminate at least one time where the unit is placed in SLO at low core flow/power operation, a mode of operation where reactor instability is a concern.

Sufficient jet pump baseline data has been gathered at Susquehanna, Units 1

and 2, that the distribution of data is well defined and is not changing from cycle to cycle.

The recirculation pump flow versus

speed, the total core flow versus recirculation pump flow, and the single loop jet pump distribution curves have had no major adjustments since the reactors have consisted of full cores of the Siemens 9x9-2 fuel design.

Testing and gathering of data will be accomplished in the same manner as in the past, albeit according to a

different schedule Furthermore, the licensee has committed to establish administrative controls to ensure SLO baseline data will be recorded under the following conditions:

1) beginning of cycle when discharged bundles are replaced with bundles of a different mechanical or thermal-hydraulic design,
2) when reactor systems or core operating strategies which can affect the baseline data are modified, and 3) if it is determined that dual loop baseline data has changed significantly.

The proposed change accomplishes the same objective as the present TSs.

Also, the change is consistent with the recommendations in General Electric Service Information Letter 330 (GE SIL 330).

The proposed change is acceptable.

3.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendment.

The State official had no comments.

4.0 ENVIRONMENTAL CONSIOERATION The amendment changes a surveillance requirement.

The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released

offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.

The Commission has previously issued a

proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (58 FR

'1509).

Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).

Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

5.0 CONCLUSION

The Commission has concluded, based on the considerations discussed

above, that:

(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed

manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor:

R. Clark Date:

December 10, 1993

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