ML18043A499
| ML18043A499 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 02/22/1979 |
| From: | Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| NUDOCS 7902280325 | |
| Download: ML18043A499 (7) | |
Text
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consumers Power company General Offices: 212 West Michigan Avenue,.Jackson, Michigan 49201
- Area Code 517.788-0550 Fep;-ua.ry 22, 1979 Mr James G Keppler Office of Inspection a.nd Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - 10CFR 50. 59 ANNUAL REPORT
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LJ Enclosed is the report of changes, tests and exl;>eriments :performed in 1978 which are re:portable under 10CFR 50. 59 (b)
- David P Hoffman (Signed)
David P Hoffman Assistant Nuclear Licensirig Administrator CC:
Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement 7 9 0 2 2 8 0 3 ;2.~
1978 Changes, Tests and Experiments Made Pursuant to 10 CFR 50.59
- 1.
F.C.#316 This modification involved the repiping of the Boronometer and Process Monitor RE-0202 to locate the Process Monitor farther from the Boronometero Safety Evaluation Summary The modification did not change the purpose or function of the system. It only extended the piping which still conformed to appropriate codes.
No unreviewed safety question existed.
- 2.
F.C.#365 This modification covered removal of Poison Rods from 'B' type fuel bundles using a special modification machine constructed by the fuel vendor.
Safety Evaluation Summary The Poison Rods were removed following an approved plant procedure covered by Technical Specification pection 3.8.
The probability of increasing the risk of an accident important to safety was not increasedo
- 3.
F.C.#376 Modifications were made to decrease the air temperature in the area of CRDM drive packages.
- 1.
Relocated CRDM Cooling Fans (V49A&B).
- 2.
A Baffle Plate was mounted on the inside of the service platform walkway.
Safety Evaluation Summary Although the head lift rig is not covered by the FSAR - damage could result to CRDM's if the lift rig were to collapse.
This modification assures that the head lift assembly will remain intact during postulated earthquake conditions.
Relocation of fans does not affect CRDM operability.
An unreviewed safety question did not exist.
- 4.
FoC.#379B This modification covered the installation of modified internals into the main steam isolation valves during the 1978 refueling outage.
Safety Evaluation Summary The new internals were designed to be more resistant to failure than the original valve internals.
Therefore, the margin of safety was increased.
An unreviewed safety q_uestion did not exist.
1978 Changes, Tests a~xperiments Made Pursuant to l~
50.59 2
- 5.
F.C.#384 This modification resulted in installing a circuit checking system for CV-3027 and CV-3056 (SIRWT miniflow recirc valves). It also covered i~stalling a key operated handswitch in parallel with SIRW tank low level contact 411.
Safety Evaluation Summary This modification was made to decrease the consequences of an accident.
The design fits the criteria that no single failure can cause undesired valve operation.
- 6.
F.C.#396 This modification involved changes to essential electrical systems to ensure their proper operation if the Containment should be flooded during a postulated LOCA.
Safety Evaluation Summary Through the installation of backup fuses in the affected circuits, additional protection was attained in the event of submergence of essential electrical equipment.
An unreviewed safety question did not exist.
F.C.#402 This modification provided a seismically qualified source of air to the seats of containment isolation valves CV-1805, 1806, 1803, 1807, 1808, 1813 and 1814.
The air has been supplied from accumulators.
Safety Evaluation Summary The containment purge valves were upgraded to assure that the "T" ring has a source of air after a seismic event.
The "T" ring itself was not modified.
An unreviewed safety question did not exist.
- 8.
F.C.#404 This modification involved the installation of equipment and logic circuits necessary to protect the reactor vessel when it is in cold shutdown (below NDTT).
Pressure protection is provided by opening the power operated relief valve at the appropriate pressure.
Safety Evaluation Summary This modification provided additional controls and methods to prevent exceeding Technical Specification pressure limits.
The margin of safety for brittle failure of the reactor vessel has been increased by this modification.
1978 Changes, Tests and Experiments Made Pursuant to 10 CFR 50.59 3
- 9.
F.C.#413 (Nuclear fuel reload "G" for use in Cycle 3).
The design of the fuel is described in XN-NF~77-41 and XN-NF-77-54.
Safety Evaluation Summary The changes in fuel design were minor and do not increase the probability or consequences of an accident.
This change did not involve an unreviewed safety question.
- 10.
S.F.C.#76-046 This specification change replaced the seal housings and diaphrams for CV-2117, 1057 and 1059 so that they will operate under post LOCA conditions.
Safety Evaluation Summary The specification change upgraded safety related equipment.
Therefore, the consequences of an accident are decreased and the margin of safety increased.
- 11.
S.F.C.#77-083 This specification change replaced time delay relays in the charging pump lube oil low pressure trip circuitry.
Safety Evaluation Summary The new relays have a more reliable repeat accuracy than the original relays.
Therefore, the margin of safe~y has been increased and no unreviewed safety question exists.
12a S.F.C.#77-096 This field change changed the feed for bus Y-01 from MCC#2 to MCC#3 and feed for diesel engine room heater fans from MCC#3 to MCC#80 to free break.er on MCC#3.
Safety Evaluation Summary ITo basic design changes were made-as a result of this modification, and no unreviewed safety question existed.
- 13.
S.F.C.#78-013 This field change resulted in the removal of the check valve and the installation of a gasketed blind flange on the Containment side of penetration #39.
(Containment heating steam supply line).
Safety Evaluation Summary T:.rJ.e margin of safety was increased by this modification by ensuring that the local leak testing results for the penetration would be acceptable.
1978 Changes, Tests and Experiments Made Pursuant to 10 CFR 50.59 4
- 14.
T-85, Out of Core Wet Sipping Procedure This procedure was conducted to identify fuel assemblies which may have contained fuel rods with defective cladding.
Safety Evaluation Summary This test was conducted in accordance with approved plant procedures.
A detailed analysis showed that no significant fission product release to the primary coolant system had resulted from any of the 33 fuel assemblies which were inspected. All assemblies sipped were reloaded into the core.
No unreviewed safety question existed.
- 15.
T-86, Visual Inspection of Palisades Core 2 Fuel Assemblies - Phase 1 An inspection was performed on six assemblies with emphasis on:
- 1.
Measurement of the poison pin gap.
- 2.
Measurement of fuel rod gap.
- 3.
The overall length of the fuel assembly guide bars.
Safety Evaluation Summary The procedure was conducted according to approved plant Operating Procedures and the Technical Specifications.
The inspection yielded no evidence of significant fuel damage and did not constitute an unreviewed safety question.
- 16.
T-95, Initial Apnroach to Critical for a New Palisades Core The purpose of using a Special Test Procedure was to provide additional surveillance for the initial criticality.
Safety Evaluation Summari; The procedure used was in accordance with plant Operating Procedures and the Technical Specifi~ations.
- 17.
T-105, Low Power Test Program for Palisades Core 3 This procedure was written to control the low power testing by designating additional test procedures for individual physics tests.
The procedure also verified certain reactor para.meters required by the Technical Specifications.
Safety Evaluation Summary Low Power Testing was accomplished using approved plant procedures written to comply with requirements of the Technical Specifications.
The probability of occurrence or the consequences of an accident were not increased.
1978 Changes, Tests and Experiments Made Pursuant to 10 CFR 50.59 5
- 18.
T-106, Zero Power All Rods Out Critical Boron Concentration Testing Safety Evaulation Summary Testing was performed using an approved procedure written to comply with requirements of the Technical Specifications and did not constitute an unreviewed safety question.
- 19.
T-107, Zero Power Rod Worth Measurements This procedure was performed to measure the worth of various control rods in different configurations and compare the measured worths predicted values.
Safety Evaluation Summary Testing was performed using an approved procedure written to comply with requirements of the Technical Specifications and did not constitute an unreviewed safety question.
- 20.
T-108 This test was performed to measure the zero power isothermal temperature coefficient and compare it with predictions.
Safety Evaluation Summary This procedure was written to comply with Technical Specification require-ments and did not constitute an unreviewed safety question.
- 21.
T-110 This test was written to determine the degree of symmetry of the core and to determine dropped rod worth.
Safety Evaluation Summary The test was performed using an approved procedure written to comply with Technical Specification requirements and did not constitute an unreviewed safety question.
- 22.
T-111, Power Escalation Test Program for Palisades Core 3 The purp0se of this test was to verify predicted values of the moderator temperature coefficient and the power coefficient at a high and low power level.
Safety Evaluation Summary The test was performed using an approved procedure written to comply with Technical Specifications requirements.
The probability of occurrence or the consequences of an accident were not increased.
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- 23.
T-112, Base Power Level Selection 6
This test was performed to determine an acceptable power level range for the performance of low power physics tests.
Safety Evaluation Summary This procedure was written to comply with Technical Specification requirements and did not constitute an unreviewed safety question.