ML20246N276: Difference between revisions

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#REDIRECT [[PY-CEI-NRR-0993, Confirms That Standby Liquid Control Test Completed & Test Acceptance Criteria Satisfied.Results Showed Total Sys Flow Exceeded 82.4 Gpm & No Evidence of Relief Valve Lift During Test,In Response to NRC ]]
| number = ML20246N276
| issue date = 05/11/1989
| title = Confirms That Standby Liquid Control Test Completed & Test Acceptance Criteria Satisfied.Results Showed Total Sys Flow Exceeded 82.4 Gpm & No Evidence of Relief Valve Lift During Test,In Response to NRC
| author name = Kaplan A
| author affiliation = CLEVELAND ELECTRIC ILLUMINATING CO.
| addressee name =
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000440
| license number =
| contact person =
| document report number = PY-CEI-NRR-0993, PY-CEI-NRR-993, TAC-62767, NUDOCS 8905190395
| title reference date = 03-15-1989
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 1
| project = TAC:62767
| stage = Other
}}
 
=Text=
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THE CLEVELAND ELECTRIC ILLUMINATING COMPANY P.O. BOX 97 5  PERRY, OHIO 44081 m TELEPHONE    (216) 259-3737  5      ADDRESS-10 CENTER ROAD FROM CLEVELAND: 241 1650 Serving The Best Location in the Nation PERRY NUCLEAR POWER PLANT Al Kaplan VCE PRESrDENT NUCLEAR GROUP                                                      MOY 1l l989 t
PY-CEI/NRR-0993L U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.      20555 Perry Nuclear Power Plant Docket No. 50-440 Standby Liquid Control Test Results (TAC 62767)
Gentlemen:
Your letter of March 15, 1989, on the subject of Perry Unit I compliance with the ATWS Rule, requested that we provide Standby Liquid Control System (SLCS) 2 pump test results. Test conditions and acceptance criteria were previously defined in our letter PY-CEI/NRR-0954L dated January 31, 1989.
We confirm that the subject test has been completed, and that test acceptance criteria have been satisfied:
: 1. Total system flow exceeded 82.4 gpm; most importantly net injection flow exceeded 85 gpm at a pump discharge pressure exceeding 1220 psig.
: 2. There was no evidence of relief valve " lift" during the test. The relief valve dise did weep, at the rate of less than 0.25 gpm, with greater than 85 gpm continuing to be delivered to the injection path.
Two pump discharge pressure remained steady at this injection rate.
Please feel free to call if you have further questions.
Very truly yours,
{            _ .
W; (An Al Kaplan
(
                                                                                                                        )
Vice President Nuclear Group WJE/sc cc:    T. Colburn NRC Resident Inspector U.S. NRC Region III g O
                                                                                                                                                        /
AfDOCK0395          890511                                                                      )                      O P              05000440 PDC
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _}}

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