ML20072B225: Difference between revisions

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#REDIRECT [[PY-CEI-NRR-1837, Special Rept:On 940515 & 0618,ECCS Manual Actuations W/ Injection Into RCS Occurred as Part of Preplanned Activities for Testing]]
| number = ML20072B225
| issue date = 08/08/1994
| title = Special Rept:On 940515 & 0618,ECCS Manual Actuations W/ Injection Into RCS Occurred as Part of Preplanned Activities for Testing
| author name = Stratman R
| author affiliation = CENTERIOR ENERGY
| addressee name =
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000440
| license number =
| contact person =
| document report number = PY-CEI-NRR-1837, NUDOCS 9408160052
| document type = REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER), TEXT-SAFETY REPORT
| page count = 2
}}
 
=Text=
{{#Wiki_filter:_ _
<      \
1                CENTEREOR
                    .        ENERGY PERRY NUCLEAR POWER PLANT                      Mai Mdress:                                  Robert A.$tratman P.O. BOX 97                                  VICE PRESIDENT NUCLEAR 10 CENTER ROAD                                  PERRY, OHIO 44081 PERRY, OHIO 44081 (216) 259-3737 l
August 8, 1994 PY-CEI/NRR-1837L                                    i U.S. Nuclear Regulatory Commission Document Control Desk Vashington, D.C. 20555 i
Perry Nuclear Power Plant Docket No. 50-440 Special Report - ECCS Injection Gentlemen:
Perry Nuclear Power Plant Technical Specification 3.5.1 requires that a Special                          l Report be submitted in accordance with Technical Specification 6.9.2 for                                l Emergency Core Cooling System (ECCS) actuations and injections into the reactor coolant system. During refueling outage four, manual ECCS actuations were performed as part of pre-planned testing to support requirements for NRC Generic Letter 89-10, " Safety Related Motor Operated Valve Testing and Surveillance." The attached Special Report provides details of these actuations and meets the reporting requirements of Technical Specification 3.5.1 Action h and 6.9.2.
If you have questions or require additional information, please contact Mr. James D. Kloosterman, Manager - Regulatory Affairs at (216) 280-5833.
Very truly yours,                                  j
                                                                                    'f/h s
                                                                          ,fu'        @%h7W-RAS DAHans Attachment cc:        NRC Project Manager NRC Resident Inspector Office NRC Region'III 1200c9 9400160052 940008                                                                                        -
PDR        ADOCK 05000440                                                                                l S                                PDR                                                                      I Operating Cornpanies                                                                            [O    l Cleveiona Eiectnc itiurninanng                                    \                                  l Toledo Edrson                                                      \                            ;\ g
 
.s PY-CEI/NRR-1837L Attachment Page 1 of 1 4
PERRY NUCLEAR POWER PLANT NRC Docket 50-440 Special Report ECCS Actuation and Injection into the RCS On May 15, 1994 and June 18, 1994, Emergency Core Cooling System (ECCS) manual actuations with injection into the Reactor Coolant System 'RCS) occurred as part of pre-planned activities for testing. This report is submitted in accordance with the requirements of Technical Specification 3.5.1 Action h which requires a Special Report (Technical Specification 6.9.2) to be submitted within 90 days in the event an ECCS actuates and injects water into the RCS.
During the last refueling outage (RF04), diagnostic testing of safety related motor operated valves (MOV) was being performed in accordance with the requirements of Generic Letter (GL) 89-10, " Safety-Related Motor-Operated Valve Testing and Surveillance." This testing included dynamic flow testing of the Low Pressure Core Injection (LPCI) system train B injection valve (1E12-F042B) and the High Pressure Core Spray (HPCS) system injection valve (1E22-F004). In order to perform dynamic flow testing of these valves, the respective systems had to be operated with flow to the reactor vessel.
During testing on May 15, 1994, the reactor was defueled with the reactor pressure vessel head removed. During testing on June 18, 1994, the plant was in Operational condition 5 (Refueling) with fuel in the vessel. Due to the plant and system conditions during this testing, these injections do not add to the number of actuation cycles to date.
There have been seven previous HPCS injections and no previous LPCI system injections. The injection nozzle usage factors are less than 0.70.
Prior to the testing, courtesy notifications to the NRC Operations Center were made utilizing the Emergency Notification System (ENS).        i These notifications were made on May 15, 1994 at 0049 and June 18, 1994 at 2050.
I
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