ML18040A840

Forwards Application for Proposed Amends 98 & 51 to Licenses NPF-14 & NPF-22,respectively,revising Tech Spec 4.8.2.1.d.2.b to Increase Load Profiles for Batteries 1D612 & 1D622

ML18040A840
Person / Time
Site:	Susquehanna
Issue date:	06/10/1987
From:	Keiser H PENNSYLVANIA POWER & LIGHT CO.
To:	Butler W Office of Nuclear Reactor Regulation
Shared Package
ML18040A841	List: ML18040A840 ML18040A842 ML18040A844
References
PLA-2867, NUDOCS 8706170167
Download: ML18040A840 (6)

Text

RE 'TORY INFORMATION DISTR IT'lQN SYSTEM <RIDB)

ACCESSION NBR:8706170167 DOC. DATE: 87/06/10 NOTARIZED: YEB DOCKET 0 FACIAL: 50-387 Susquehanna Steam Electric Stationi Unit iI Pennsglva 05000387 50-388 Susquehanna Steam Electric Stationi Unit 2I Pennsglva 05000388 AUTH. NAME AUTHOR AFFILIATION KEISERI H. N. Pennsylvania Power 5 Light Co.

RECIP. NAME 'ECIPIENT AFFILIATION BUTLERI M. R. ProJect Directorate I-2

SUBJECT:

Forwards application for proposed Amends 98 h 51 to Licenses

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DPR-14 Cc DPR-22 respectively revising Tech Spec

4. 8. 2. 1. d. 2. b to increase load proFiles for Batteries 1D612 8c 19622.

DISTRIBUTION CODE: AOOID TITLE: OR COPIES RECEIVED: LTR Submittal: General Distribution

~ ENCL + SIZE:

NOTES: 1 c g NMSS/FCAF/PM. i LPDR 2c g s Trans cr p ts. 05000387 icy NMBS/FCAF/PM. LPDR 2cgs Transcripts. 05000388 REC I P IENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDi-2 LA 0 PDi-2 PD 5 5 THAD*NIi M 1 1 INTERNAL: ACRS 6 6 ARM/DAF/LFMB 0 NRR/DEBT/*DE NRR/DEST/ADS 1 1 NRR/DOEA/TSB 1 1 8/ILRB 1 1 OQC/HDB2 1 0 FILE 01 1 EXTERNAL: Echo BRUBKE> S 1 1 LPDR NRC PDR 1 1 NBIC NOTES:

TOTAL NUMBER OF COPIES REGUIRED: LTTR 28 ENCL 25

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Pennsylvania Power 8 Light Company Two North Ninth Street ~ Allentown, PA 18101 ~ 215 / 7705151 JUg lg 3SB7 Harold W. Keiser Vice President-Nuclear Operations 21 5/770-7502 Director of Nuclear Reactor Regulation Attention: Dr. W. R. Butler, Project Director Project Directorate I-2 Division of Reactor Projects U.S. Nuclear Regulatory Commission Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION PROPOSED AMENDMENT NO. 98 TO NPF-14 AND PROPOSED AMENDMENT NO. 51 TO NPF-22 125V D.C. LOAD PROFILES PLA-2867 FILES A17>>20A, R41-2, S002

Dear Dr. Butler:

Pursuant to 10CFR50.90, Pennsylvania Power 6 Light Co. requests amendments in the form of Technical Specification changes, to Operating Licenses NPF-14 and NPF-22 for Susquehanna Steam Electric Station Units 1 and 2.

Specifically, we request Specification 4.8.2.1.d.2.b be modified to increase the load profiles for batteries 1D612 and 1D622. This is necessary to accommodate the installation of ATWS Alternate Rod Injection solenoid valves.

Marked-up copies of the affected technical specification pages are enclosed.

The proposed changes do not:

(1) Involve an increase in the probability or consequences of an accident previously evaluated. FSAR Section 8.3.2.1.1.4 states the station batteries have sufficient capacity without the charger, to independently supply the required loads for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The Technical Specifications require the batteries be surveilled to a dummy load which is greater than the design loads. To demonstrate the batteries have adequate capacity to supply the proposed load profile, a calculation was performed by our Engineering department. This calculation in part is based on IEEE 485. In particular, cell sizing worksheets were prepared for the new loads. These worksheets determine the number of positive plates the specific battery must have to supply the given load profile. For the proposed profile, and considering worst case which is a battery electrolyte temperature of 60'F, the 1D612 and 1D622 batteries were to have adequate capacity. 'emonstrated (2) Create the possibility of a new or different kind of accident from any accident previously evaluated. As stated in Part(l), the batteries have sufficient capacity for the proposed load profile, thus enabling them to J ~/~ M~IC 8706170167 870b10 PDR ADOCK 05000387 P PDR gcc,

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JUN l0 1987 FILES A17-20IR41-2 PLA-2867 Dr. W. R. Butler perform their intended function. Any postulated accident resulting from this change is bound by previous analysis.

(3) Involve a reduction in the margin of safety. In accordance with IEEE 450, the rated battery capacity is 25 percent greater than required. This margin allows replacement of the battery when its capacity has decreased to 80 percent of its rated capacity (100 percent of design load). This margin has been maintained and included as part of the calculation referred to in Part(l).

We request these amendments be approved and made effective'at the conclusion of the Unit 1 3rd refueling and inspection outage. (Currently scheduled to commence September 12, 1987 and end November 13, 1987).

Pursuant to 10CFR170.22, the appropriate fee is enclosed.

If you have any questions, please contact D. J. Walters at (215)770-6536.

Very truly yours, H. W. Keiser Vice President Nuclear Operations cc: lRRC 'Document Control Desk (~o iginal)~

NRC Region I Mr. L. R. Plisco, NRC Resident Inspector Mr. M. C. Thadani, NRC Project Manager

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