ML20133P127
| ML20133P127 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold |
| Issue date: | 10/18/1985 |
| From: | Mineck D IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| DAEC-85-846, NUDOCS 8510310140 | |
| Download: ML20133P127 (6) | |
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j F-lowa Electric Light and Ibwer Company October 18, 1985 L- -
DAEC-85-846 Fu Mr. James G. Keppler Regional Administrator U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137
Subject:
Duane Arnold Energy Center Op. License No:
DPR-49 Docket No: 50-331 DAEC Restart Testing at Beginning of Cycle 8
Reference:
Power Uprate for the DAEC, NG-84-2518, McGaugby (IE) to Denton (NRC), August 17, 1984
Dear Mr. Keppler:
This letter transmits the results of the Startup Test Program which was conducted at the Duane Arnold Energy Center at the beginning of Cycle 8.
This test progmm was performed in accordance with Section 3.3 of the DAEC Surveillance Manual, Surveillance Requirements for Startup and Shutdown, and the referenced letter, to which the application for power uprate was attached. As part of this application, Iowa Electric committed to conducting tests at the old rated power of 1593 MWth.
Some of these tests would be repeated at the uprated power of 1658 MWth, with the results being compared to expected values.
Each test which was performed as part of this Power Uprate test program was satisfactorily completed, with the results comparing favorably to the values which were expected.
The application for power uprate contained one test, RE-15, Control Rod Friction Testing and Insert / Withdraw Timing, which was not performed because plant conditions prohibited conducting this-procedure until near the end of the outage. By this time, each rod had been exercised and was determined to be operable.
Consequently, it was determined that this test was redundant to the exercises which had already taken place and was therefore not performed.
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i Duane Arnold Energy Center Op. License No:
DPR-49 Docket.No:
50-331 DAEC Restart Testing at Beginning of Cycle 8 Page 2 i
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This report is being submitted in accordance with Section 6.11.1 of the DAEC Technical Specifications. A listing of the tests performed and the status of the startup while the test was being performed is presented in the i
attachment to this letter. All data for these tests are available at the l
Duane Arnold Energy Center.
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Sincerely yours, i
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i to-18-91 Danie L. Mineck i
Plant Superintendent-Nuclear Duane Arnold Energy Center j
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Attachment:
Listing of Surveillance Performed in Support of Cycle 8 Startup cc:
(All w/a), M. Brandt L. Liu S. Tuthill R. McGaughy M. Thadani NRC Resident Canmitment Control 840306 File: A-118h, A-117, SPF-95 i
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DAEC-85-846 October 18, 1985 ATTACHMENT: Listing of Surveillances Performed in Support 3
of Cycle 8 Startup STP TITLE PRIOR TO STARTUP 1.
55A001 FUEL STORAGE FACILITIES K LIMIT CHECK
- gyg, (PRIOR TO STARTUP) 2.
412A001 MAPLHGR CURVES CHECK (PRIOR TO STARTUP) 3.
41A004
- IRM TRIP FUNCTIONAL TEST & CALIBRATION (WITHIN I
ONE WEEK PRIOR TO STARTUP) 4.
41A017
5.
42C004
- SRM/IRM DETECTOR NOT IN STARTUP POSITION FUNCTIONAL TEST (WITHIN ONE WEEK PRIOR TO STARTUP) 6.
420005
- SRM TRIP FUNCTIONAL TEST & CALIBRATION (WITHIN l
ONE WEEK PRIOR TO STARTUP)
I 7.
42A004 MAIN STEAM LINES HIGH FLOW INSTRUMENT
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FUNCTIONAL TEST / CALIBRATION (PRIOR TO STARTUP)
I 8.
41A007 TURBINE CONTROL VALVE FAST CLOSURE RESPONSE j
TIME TEST AND INITIATE LOGIC (PRIOR TO STARTUP) 9.
41A018 APRM FLOW BIAS INSTRUMENT FUNCTIONAL TEST l
(PRIOR TO INITIAL R00 WITHDRAWAL) l 10-47A002 PRIMARY CONTAINMENT LEAK RATE TEST d
(PRIOR TO STARTUP) i
- 11. 47A003 CONTAINMENT LEAK TIGHTNESS TEST-TYPE B PENETRATIONS (PRIOR TO STARTUP) 1 i
- 12. 47A005 CONTAINMENT ISOLATION VALVE LEAK TIGHTNESS l
TEST-TYPE C PENETRATIONS (PRIOR TO STARTUP)
- 13. 42F001 REACTOR WATER LEVEL AND PRESSURE INSTRUMENTS CALIBRATION (PRIOR TO STAP, TUP) 14, 41A025 REACTOR HIGH PRESSURE INSTRUMENT RESPONSE TIME CHECK (PRIOR TO STARTUP) l
- 15. 42A001 DAILY AND SHIFT INSTRUMENT CHECKS (PRIOR TO AND THROUGHOUT STARTUP)
- 16. 468001 RX COOLANT GAMMA & IODINE ACTIVITY (PRIOR TO STARTUP) 1 of 4 Y y
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DAEC-85-866 i
October 18, 1985 ATTACHMENT: Listing of Surveillances Performed in Support of Cycle 8 Startup STP TITLE
- 17. 41A001 REACTOR HIGH PRESSURE INSTRUMENT FUNCTIONAL TEST AND CALIBRATION (PRIOR TO STARTUP)
- 18. 468003 RX COOLANT CHLORIDE ION & CONDUCTIVITY ANALYSIS (PRIOR TO STARTUP)
- 19. 41A021 FIRST STAGE TURBINE PRESSURE PERMISSIVE INSTRUMENT FUNCTIONAL TEST AND CALIBRATION (PRIOR TO STARTUP)
- 20. 438003
- RWM/RSCS CAPABILITY TEST (IMMEDIATELY PRIOR TO INITIAL ROD WITHDRAWAL)
STARTUP AND LOW-POWER OPERATION
- 21. 46A003
- HEATUP & C00LDOWN RATE LOG (DURING STARTUP)
- 22. 43A001
- SHUTDOWN MARGIN TEST (DURING R0D WITHDRAWAL TO CRITICAL)
- 23. 470004
- MAIN STEAM ISOLATION VALVES (IMMEDIATELY AFTER PLACING MODE SWITCH IN RUN AND CONTINUING POWER INCREASE)
- 24. 45E001-Q RCIC SYSTEM OPERABILITY TESTS (150 psi REACTOR PRESSURE)
- 25. 450001-Q HPCI SYSTEM QUARTERLY OPERABILITY TESTS (150 psi REACTOR PRESSURE)
- 26. 42C001 APRM INSTRUMENT FUNCTIONAL TEST AND CALIBRATION (AFTER PLACING MODE SWITCH IN RUN)
- 27. 41A016 APRM HIGH FLUX & INOPERATIVE INSTRUMENT FUNCTIONAL TEST / CALIBRATION (AFTER PLACING MODE SWITCH IN RUN)
- 28. 42G001
- REACTOR HIGH PRESSURE RECIRCULATION PUMP TRIP INSTRUMENT FUNCTIONAL TEST AND CALIBRATION (WITHIN 24 HOURS AFTER PLACING MODE SWITCH IN RUN)
- 29. 41A013-Q STEAM LINE HIGH RADIATION (DURING POWER OPERATION)
- 30. 41A013-W STEAM LINE HIGH RADIATION (DURING POWER OPERATION) 2 of 4
o DAEC-85-846 October 18, 1985 ATTACHMENT:
Listing of Surveillances Performed in Support of Cycle 8 Startup STP TITLE 31.
SpTP-123 LOW-POWER RBM FUNCTIONAL CHECK (15% Power)
- 32. 42F007
- APRM GAIN ADJUSTMENT CALIBRATION (PRIOR TO 20%
CORE THERMAL POWER) 33, 42C002 R0D BLOCK MONITOR FUNCTIONAL TEST AND CALIBRATION (27-30% POWER)
- 34. N/A VERIFICATION OF PERFORMANCE OF TURBINE BYPASS SCRAM INTERLOCKS AND RSCS INTERLOCK PRESSURE (30% POWER) 35.
43C001
- SCRAM INSERTION TIME TEST (38% POWER)
- 36. 41A015
- LPRM INSTRUMENT CALIBRATION (38% POWER)
MEDIUM AND HIGH POWER OPERATION
- 37. 43E001 APRM/LPRM BASELINE NOISE DATA COLLECfl0N FOR TWO LOOP OPERATION (45% Core Flow)
- 38. APPENDIX E
- APRM GAIN ADJUSTMENT CALIBRATION (1500-1593 MWth) 0F 42A001
- 39. 43D001
- REACTIVITY ANOMALIES CHECK (1500-1593 MWth)
- 40. 46B001
- RX COOLANT GAMMA & I0 DINE ACTIVITY (1500-1593 MWth) 41, 41A015
- LPRM INSTRUMENT CALIBRATION (1500-1593 MWth)
- 42. 468003
- RX COOLANT CHLORIDE ION & CONDUCTIVITY ANALYSIS (1500-1593 MWth) 43.
PREDICTOR
- AXIAL POWER SHAPE COMPARISON: CHECK REACTOR PARAMETERS (AXIAL AND RADIAL FLUX, LOAD LINE, THERMAL LIMITS, K-EFFECTIVE) AGAINST THE PREDICTED PARAMETERS WHICH WERE PREDICTED AT THE PREVIOUS POWER STATES LISTED BELOW.
65% POWER (PREDICTED FROM 38% POWER) 80% POWER 90% POWER 95% POWER 100% POWER 3 of 4 4
DAEC-85-846 October 18, 1985 ATTACHMENT: Listing of Surveillances Performed in Support of Cycle 8 Startup STP TITLE
- 44.. APPENDIX E
- APRM GAIN ADJUSTMENT CALIBRATION (1658 MWth) 0F 42A061
- 45. 430001
- REACTIVITY AN0MALIES CHECK (1658 MWth)
- 46. 468001
- RX COOLANT GAMMA & IODINE ACTIVITY (1658 MWth)
- 47. 468003
- RX COOLANT CHLORIDE ION & CONDUCTIVITY ANALYSIS (1658 MWth)
- 48. 41A013-Q STEAM LINE HIGH PADIATION (1658 MWth)
- 49. 41A013-W STEAM LINE HIGH RADIATION (1658 MWth)
This test was part of the Power Uprate Test Program.
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