ML20093B698
| ML20093B698 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 10/05/1984 |
| From: | Kemper J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| CON-#484-453 OL, NUDOCS 8410100193 | |
| Download: ML20093B698 (6) | |
Text
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4 PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHIA, PA.19101 12151 e41-4 502 vic E +w EsIDE NT c................u...
Mr. A. Schwencer, Chief Docket Nos.:
50-352 Licensing Branch No. 2 50-353 Division of Licensing U. S. Nuclear Regulatory Comnission Washington, D.C. 20555
Subject:
Limerick Generating Station, Units 1 and 2 Request for 7dditional Information (RAI)
Procedures and Test Review Branch (PTRB)
References:
(1)
V. S. Boyer to A. Schwencer letter dated Sepbmi;er 27, 1984.
(2)
J. S. Kmper to A. Schwencer letter dated Septenber 28, 1984.
(3)
R. J. Stipcevich (PE00) and R. Becker (NBC) telecons dated 10/2 and 10/5/84.
File:
GOVT 1-1 (NRC)
Dear Mr. Schwencer:
In the reference telephone calls tha PTRB reviewer requested that we revise our draft responses to FSAR Table 14.2-3, Startup Test Procedure (STP)-10, FSAR Figure 14.2-5, Startup Test Sequence and RAI 460.13 recently transmitted to you in reference letters 1 and 2.
The attached draft responses have been changed to incorporate a reference source to the acceptance criteria in STP-10, the non-deletion of STP-37 ard a brief description of the DC voltage verification test in RAI 460.13 to be cmpleted prior to exceeding five percent power.
The attached revised FSAR draft page changes will be incorporated into the FSAR, exactly as they appear in the attachments in the revision scheduled for Novmber,1984.
Sincerely, i
RJS/gra/10038403 cc: See Attached Service List W An# U NE B 08' A
I
c cc: Judge Helen F. Foyt (w/o enclosure)
Judge Jerry Harbour (w/o enclosure)
' Judge Richard F. Cole (w/o enclosure)
Judge Christine N. Kohl (w/o enclosure)
Judge Gary J. Edles (w/o enclosure)
Judge Reginald L. Gotchy (w/o enclosure)
Troy B. Conner, Jr., Esq.
(w/o enclosure) i Ann P. Hodgdon, Esq.
(w/o enclosure)
Mr. Frank R. Romano (w/o enclosure)
Mr. Robert L. Anthony (w/o enclosure)
Ms. Phyllis Zitzer (w/o enclosure)
Charles W. Elliott., Esq.
(w/o enclosure)
~
Zori G. Ferkin, Esq.
(w/o enclosure)
Mr. Thomas Gerusky (w/o enclosure)
Director, Penna. Emergency (w/o enclosure)
Management Agency Angus Inve, Esq.
(w/o enclosure)
David Wersan, Esq.
(w/o enclosure)
Robert J. Sugarman, Esq.
(w/o enclosure)
Martha W. Bush, Esq.~
(w/o enclosure)
Spence W. Perry, Esq.
(w/o enclosure)
Jay M. Gutierrez, Esq.
(w/o enclosure)
Atomic Safety & Licer. sing Appeal Board (w/o enclosure)
Atomic Safety & Licensing Board Panel (w/o enclosure)
Docket & Service Section (w/o enclosure)
James Wiggins (w/o enclosure)
Timothy R. S. Campbell (w/o enclosure)
A
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TABLE 14.2-3 (Cont'd)
(Page 5 of 24)
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cparnibwtL lAcceptanceCriteria_-SRMsarer-!E5:rt:fndre V
the designed range for a cold clean core. """"r ruffiri^-6?;
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>e (STP-9) Water Level Reference Leo Temperature (Formerly SUT-7) l 0
Test Obiective - The test objective is to demonstrate the calibration and agreement of the installed reactor vessel water levelinstrumentation[23: 7:ri :: h:t si..1, m.C L 1: r.:
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Prerequisites - The following are determined and recorded:
elevations of instrument taps, condensing' chambers, head chambers indicating zero water level, and instrument ranges.
The reactor is in a steady-state condition during each stage of testing.
Air temperature in the vicinity of the level columns is stabilized.
Test Method - The test will be done at rated temperature and 1
pressure and under steady-state conditions; the reference leg temperature will be measured and compared to the value assumed during-initial calibration.
If the difference exceeds operating
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measured value.
tolerances, the instruments will be recalibrated using the I
Acceptance Criteria - The installed reactor water level indication and controls provide accurate information and sufficient operating tolerances under normal operating s
conditions.
(STP-10) IRM Performance (Formerly SUT-8) l Test Obiective - The test objective is to demonstrate IRM system
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3 response to neutron flux and IRM overlap with the S ems.
j Prerequisites - Fuel loading is completed, and the reactor is just critical.
IRM gains are set at maximum for conservatism.
Test Method - After criticality and when flux level is t
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'suiticient, IRM response to neutron flux anr**' "'he IRM-SRM D
overlap is verified.
The SRMs and IRMs may then be taken out of r
non-coincident scram.
Following average power range monitor
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(APRM) calibration in gecordance with another procedure, the IRM
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(Page 6 of 24)
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Acceptance Criteria - Pesulting IRH dl--'a---
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'M K.s1NSug fjsuy5 (STP-11) Local Power Rance Monitorino(LPRM) Olibration (ForWerl SUT-9)
Test Objective - The test objective is to calibrate the LPRM system.
Prerequisites - Reactor power and LPRM gains are sufficient to observe chamber response to the adjacent control rod during calibration of any LPRMs.
The ability of the APRH system to provide input to the reactor protection system is maintained during this test.
The process computer or offline computer is available.
Test Method - The core is operated in a specified test condition, for a period sufficient to obtain short-term equilibrium conditions.
LPRMs are calibrated in accordance with the calibration procedure.
The meter reading of each LPRM chamber is proportional to the average heat flux in the four adjacent fuel
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rods at the height of the chamber.
Acceptance Criteria - LPRM calibration, in accordance with the n
procedure, is satisfactorily completed.
i (STP-12) APRM Calibration (Formerly SUT-10) l Test Obiective - The test objective is to calibrate the APRH system.
Prerequisites - The core is at steady-state condition at the desired power level and core flow rate.
Control rod positions and core flow are not changed during the time data are taken for these. calibrations.
' Test Method - With the core'in a steady-state condition, JL cal
' th.pulations are made of the percent of rated power"2.. Jim-ucu by heat balance /S:
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The APRMs are calibrated to agree with the calculated power value.
Acceptance Criteria - The APRMs are calibrated to read equal to or greater than the calculated core thermal power.
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OUESTION 64~.13 ~(section 14.2.12) j For DC Power System tests (P-2.1, P-88.1), state your plans to verify that individual cell limits are not exceed during the design discharge test and to demonstrate that the DC loads will function as necessary to assure plant safety at a battery terminal voltage equal to the acceptance criterion that has been established for minimum battery terminal voltage for the discharge load test.
Assure that each battery charger is capable of floating the battery on the bus or recharging the completely discharged battery within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> while supplying the largest combined demands of the various steady-state loads under all plant operating conditions.
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RESPONSE
The procedure abstract for preoperational test P-2.1 has been changed A o include these requirements.
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