PY-CEI-NRR-0598, Forwards Rept Re 10CFR50.59 Changes to Initial Test Program. Rept Includes All Changes Made from 870110-0210
| ML20212A896 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 02/26/1987 |
| From: | Edelman M CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| PY-CEI-NRR-0598, PY-CEI-NRR-598, NUDOCS 8703030435 | |
| Download: ML20212A896 (4) | |
Text
r THE CLEVELAND ELECTRIC ILLUMIN ATING COMP ANY P.O. BOX 5000 - CLEVELAND, OHIO 44101 - TELEPHONE (216) 622-9800 - ILLUMINATING BLDG.
- 55 PUBLICSOUARE Serving The Best Location in the Nation MURRAY R. EDELMAN SR VICE PRESCENT NUCLE A R February 26, 1987 PY-CEI/NRR-0598 L Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Perry Nuclear Power Plant Docket No. 50-440 Report of 10 CFR 50.59 Changes to the Initial Test Program
Dear Sir:
Enclosed is a report of changes to the Initial Test Program made in accordance with Operating License Condition 2.C(4) and 10 CFR 50.59.
This report includes all such changes made from January 10, 1987 through February 10, 1987.
If you have any questions, please feel frae to call.
Very tru1y t
s, Murray. Edelm n Senior Vice President Nuclear Group MRE:njc Enclosure cc:
P. Leech J. Silberg, Esq.
K. A. Connaughton gl US:RC, Region III I
B703030435 870226 PDP ADOCK 05000440 PDR
F Attachment PY-CEI/NRR-0598 L
?
SAFETY EVALUATION
SUMMARY
SE 87-0028 I.
GENERAL INFORMATION FINAL APPROVAL FSAR DOCUMENT DATE SECTION STCN-023A-3-4 01/22/87 14.2.12.2.20.1.d Acceptance Criteria for Level 3: Item 4 II.
DESCRIPTION This Safety Evaluation was performed to evaluate the change to the Level 3 Acceptance Criteria concerning the Feedwater Pump minimum flow recirculation control valve response testing.
The criteria in the FSAR and the test will be changed to use the words specified in GE FDDR KL1-1226 concerning response testing. The Level 3. Item 4 criteria will now read, "All auxiliary which have a direct impact on reactor level and feedwater control (e.g., feedpump minimum recirculation flow valve control) should be functional, responsive, and stable. For example, testing should demonstrate that the minimum flow valve controls are fast enough to avoid pump trips and yet slower than the feedwater startup level controller to avoid possible reactor flux scrams due to a cold water slug."
III.
SUMMARY
The Safety Evaluation was prepared to allow the Feedwater minimum flow valve test to be changed in accordance with the revision to the GE Startup Test Specification specified by GE FDDR KL1-1226.
Implemented 2/12/87
Attachment PY-CEI/NRR-0598 L
?
SAFETY EVALUATION
SUMMARY
SE 87-0029 1.
GENERAL INFORMATION FINAL APPROVAL FSAR ooCuMEwr DATE SECTION STI-G33-070 R2 01/27/87 TABLE 14.2-2 II.
DESCRIPTION This Safety Evaluation was performed to evaluate the performance of Reactor Water Cleanup, Blowdown Mode Test in Test Condition 1 Table 14.2-2 in the FSAR test will be changed to indicate performance of the STI No. 70 in Test Condition 1.
The blowdown test had been performed at similar plant conditions in Test Condition Heatup and is being repeated in TC 1 after the test is revised to include new data sheets based on the TBCCW flows and temperatures observed during the initial performance of the test.
III.
SUMMARY
The Safety Evaluation was prepared to allow performance of the Reactor Water Cleanup System Blowdown Test in Test Condition 1.
F Attachment PY-CEI/NRR-0598 L SAFETY EVALUATION
SUMMARY
SE 87-0040 1.
GENERAL INFORMATION FINAL APPROVAL FSAR DOCUMENT DATE SECTION STCN-023A-3-5 02/02/87 14.2.12.2.20.1.d Acceptance Criteria for Level 3: Item 1 II.
DESCRIPTION This Safety Evaluation was performed to evaluate a change to the Level 3 Acceptance Criteria concerning the response of level or flow sensors in Feedwater Flow Control System.
The criteria in the FSAR and the test will be changed to use the values specified in the GE FDDR KL1-1233 concerning response testing.
'."he Level 3. Item 1 criteria for Bandwidth will be changed from 4.0 radians /second to 2.0 radians /second and the equivalent time constant will be change from 0.25 seconds to 0.5 seconds. This change accounts for the use of the Rosemount model 1151 dp square root transmitters.
III.
SUHHARY This Safety Evaluation was prepared to allow the Level 3 Acceptance Criteria in the Feedwater Control System test to be changed in accordance with the revision to the GE Startup Test Specification specified by GE FDDR KL1-1233.