ML20132C974
| ML20132C974 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 07/10/1985 |
| From: | Ullrich W PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| CON-#385-891 OL, NUDOCS 8509270212 | |
| Download: ML20132C974 (5) | |
Text
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RELATED CORMM MCKETED us.w' PHILADELPHIA ELECTRIC COMPANY h3 p2 2301 MARKET STREET P.O. BOX 8699 PHILADELPHIA, PA.19101 0FFicE OF SECRE TA L v 000.4ETmG & SERvih~
3, RANCH mm e41-400o t
July 10, 1985 O
Dccket No. 50-352 Dr. Thomas E.
Murley, Administrator U. S. Nuclear Regulatorv Commission Region I 631 Park Avenue King of Prussia, PA 19406
SUBJECT:
Special Report - Reactor Core Isolation Cooling (RCIC) q System Actuations and Injections - Limerick Generating Station - Unit 1, Revision 1 PEFERENCE:
Technical Specifications 3.7.3.h and 6.9.2 Dear Dr. Murleys
-This revised Special Report adds a description of one additional RCIC injection which was performed under the Startup Test Proaram but was not identified during the review of the completed Startup Test Procedures (STPs).
This injection was performed under STP 14.4-1, documented as Test Exception Report (TER) 107'hv General Electric as the result of a RCIC turbine trip which occurred while performing the test, and was identified during a subsequent review.
A description of this RCIC injection is included in the body of this report and is identified by a vertical bar in the margin.
The original Special Report was submitted pursuant to l
the requirements.of Limerick Generating Station Technical Specification 3.7.3.b which states that, "In the. event the RCIC system is. actuated land injects water into the reactor coolant system, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.", and Technical Specification 6.9.2 which states that, "Special Reports shall be submitted to the Regional Administrator of the Regional Office of
'the-NRC within the time period specified foi each report.'
s This report concerns the occurrence of eight Reactor l
Core Isolation Cooling (RCTC) system actuations and injections 8509270212 ' 50710
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d PDR ADOCK 05000352 S
Dr. Thomas E. Murley July 10, 1985 Page 2 into the reactor coolant system during startup testing of Unit No. 1.
None of the nicht PCIC vessel injections wers l
unanticipated nor the result -of safety system action from abnormal plant conditions, but were performed under the purview of the startup test program and directed by Startup Test Procedures.
Since these injections were designed into the startup test program, there were no adverse effects on the reactor vessel or the PCIC systen-as a result of the injections.
Two injections were automatic quick etarts at less than 3% rated power with the dome pressure at approximately 150 psig.
The six l
remaining injections occurred at less than 4% rated power with the dome pressure at 920 psig.
Four were automatic quick starte and two were manual. slow starts.
l Delow.is a description of each of the PCIC system actuation and injection events.
On February 77, 1985, under what was originally STP 14.4-1, but was documented as TER.107, an intentional PCIC injection into the reactor vessel,.was performed.
This injection consisted of a RCIC slow start in the manual mode, wi th flow step changes up to 600 gpm.
Reactor parameters for this injection were as follows:
Power level less than 4% of rated, reactor vessel dome pressure 920 psig, and moderator temperature 520 degrees F.
RCIC pump suction was lined up to the Condensate Storage Tank and pump discharge pressure was approximately 990 psig to achieve 600 ppm.
This injection represents the first RCIC actuation cycle to-date.
On February 27, 1985 Startup Test Procedure (STP) 14.4-1, "RCIC Controller Optimitation During RPV Injection at Rated Pressure", was performed.
The test involved two intentional PCIC injections into the, reactor vessel.
The first injection consisted of a RCIC slow start in manual mode, with flow step changes up to 600 gpm to optimize controller settings.
The second injection consisted of a RCIC quick start in automatic mode to a flowrate of 600 ppm with the same controller settings from the first injection to check control system stability.
Reactor parameters'for both injections were as follows:
i Power level less than.4% of rated, dome pressure 920 psig, and moderator temperature 520 degrees F.
RCIC pump suction for both injections was. lined up to the Condensate Storage Tank (CST) and pump discharge pressure was approximately 990 psig to achieve 600 qpm.
These two injections represent the second and third RCIC l
actuation cycles to date.
On March 1, 1985 Startup Test Procedure (STP) 14.5-1,
" Stability Check CST to RPV at 150 PSIG", was performed.
The test involved one intentional PCIC injection into the reactor vessel.
This injection ' consisted of a RCIC quick start in
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1
Dr. Thomas E.'Mur3e'y July 10, 1985 4
Page 3 automatic mode to a flowrate of 600 gpm.
Flow step chances were performed such that RCIC flowrate varied between-535 and 610 gnm.
Reactor parameters for this injection were as followc:
Power level less than 3% of rated, reactor vessel dome pressure 160 psig, and moderator temperature 360 degrees F.
PCIC pump suction was lined up to the Condensate Storage Tank and pump discharge pressure was approximately 220 psig to achieve 600 gpm.
This injection represents the fourth RCIC actuation cycle to l
date.
On April 3, 1985 Startup Test Procedure (STP) 14.5-2,
" Stability Check CST to RPV at 150 PSIG", was performed.
The test-involved one intentional PCIC injection into the reactor vessel.
This injection consisted of a RCIC quick. start in automatic mode, to a flowrate of 600 gpm to prove the RCIC system
~
operable following maintenance.
Reactor parameters for this injection.were as follows:
Power level less than 3% of rated, dome pressure 150 psig, and moderator temperature 355 degrees F.
PCIC pump suction was lined up to the Condensate Storage Tank and' pump discharge pressure was approximately 200 psig to achieve 600'gpm.
This. injection represents the fif th RCIC actuation cycle to date.
l l
On April 6, 1985 Startup Test Procedure'(STP) 14.6-1, "RCIC Cold Quickstart at Rated Pressure-CST to RPV", was performed.
The test involved one intentional PCIC injection into the reactor' vessel.
This injection consisted of a RCIC ouick start in automatic mode to a flowrate of 600 gpm.-
Reactor ~ parameters for this injection were as follows:
Power level less than 4% of rated, dome pressure'approximately 920 psig, and moderator temperature 520 degrees F.
RCIC pump suction was lined up to the Condensate Storage Tank and pump discharge pressure was approximately 990 psig to achieve 600 gpm.
This injection represents the sixth RCIC actuation cycle to date.
l On April 9L, 1985 Startup Test Procedure (STP) 14.6-2, "RCIC Cold Dufckstart at Rated Pressure-CST to RPV", was performed.
The test involved one intentional RCIC injection into the reactor vessel.- This injection-consisted ofEa RCIC ouick start in automatic. node to a flowrate of 600 gpm.
Reactor parameters for this injection were as follows:
Power level less than 4% of rated, dome. pressure approximately 920 psig,.and moderator temperature degrees F.
RCIC pump suction was lined up to the Condens.
' torage Tank and pump discharge pressuro was approximately v90 psig to achieve 600 opm.
.This injection represents the seventh RCIC actuation cycle to l
date.
Dr. Thomas'E. Murley July 10, 1985 Page 4 On April 17, 1985 Startup Test Proccoure (STP) 14.6-3, "RCIC Cold Ouickstart at Rated Pressure-CST to PPV", was performed.
The test involved one intentional PCIC injection into the, reactor vessel.
This injection consisted of a RCIC cuick start in automatic mode to a flowrate of 600 gpm.
Peactor parameters for this injection wer.e as follows:
Power level less than 4% of rated, dome pressure approximately 920 psig, and moderator temperature 520 degrees F.
RCIC pump suction was lined up to the Condensate Storage Tank and pump discharge pressure was approximately 990 psig to achieve 600 opm.
This injection represents the eighth RCIC actuation cycle to l
date.
Since these activities occurred as a result of startup testing, no corrective action is to be taken.
We regret _any inconvenience that may have resulted from this omission.
Should you require additional information, please do not hesitate to contact us.
Very truly yours, TQ&>.-
./:, 7,.s f
f ]*f'g&! Q.m-1/k W. T. Ullrich Superintendent Nuclear Generation Division E. M. Kelly,'ISenior Resident Inspector ec See Attached Service List 8
1 cc Judge Helen F. Hoyt Judge Jerry Harbour i
Judge Richard F.
Cole Troy B. Conner, Jr.,
Esq.
l Ann P. Hodgdon, Esq.
l Mr. Frank R.
Romano l
Mr. Robert L. Anthony
[
Ms. Phyllis Zitzer Charles W. Elliott, Esq.
Zori G.
Ferkin, Esq.
j Mr. Thomas Gerusky Director, Penna. Emergency Management Agency Angus Love, Esq.
David Warsan, Esq.
i Robert J. Sugarman, Esq.
Kathryn S. Lewis, Esq.
Spence W. Perry, Esq.
Jay M. Gutierrez, Esq.
Atomic Safety & Licensing Appeal Board i
Atomic Safety & Licensing Board Panel Docket & Service Section (3 Copies)
E. M. Kelly I
Timothy R. S. Campbell i
i July 3, 1985 e
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