ML20196J278
| ML20196J278 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 12/31/1987 |
| From: | Frisch R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| References | |
| NUDOCS 8803140235 | |
| Download: ML20196J278 (16) | |
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ATTACHMENT Consumers Power Company Big Rock Point Plant Docket 50-155 l
ANNUAL REPORT OF FACILITY CHANGES. TESTS AND EXPERIMENTS March 10, 1988 14 Pages Td IC0188-0014A-BT01 [
8803140235 871231 PDR ADOCK 05000155 R DCD
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Facility Changes (FC)
FC-436: Well Water Line Replacement and Relocation This change replaced the 3" carbon steel well water line from the Well House to the Screen House with a 4" PVC line becausa of failures due to corrosion.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
FC-590: Install Tell-Tales on RV-5028. -5029. -5032 This change consisted of installing three tell-tales to detect leakage through RV-5028 and RV-5029 (Heat Exchangers #1 & #2. shell side relief valves) on the reactor cooling water side of the shutdown heat exchangers and RV-5032 (non-regen heat exchanger relief valve, shell side) on the reactor cooling water side of the non-regenerative heat exchanger.
The safety evaluation concluded raat this change did not constitute an un-reviewed safety question. .
FC-591: Redundant Valves. Scram Dump Tank This change added redundant valving in both the scram dung tank vent line and drain line on the Control Rod Drive System to further reduce the probability of a LOCA through the scram dump tank drain and/or vent valve.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
FC-599Bt Replacement of Neutron Monitoring System .
This change replaced startup channels 6 and 7 of the Neutron Monitoring System due to the unavailibity of parts for the other equipment.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
FC-603: Emergency Lighting Upgrade This change involved upgrading the existing Big Rock emergency lighting so as to be consistent on the type of emergency lighting units utilized through-out the plant and to ensure that those units with the Appendix "R" (Alternate Shutdown System) modification meet the eight hour minimum operational require-ment.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
IC0188-0014A-BT01
ATTACHMENT I Consumers Power Company Big Rock Point Plant Docket 50-155 FACILITY CHANGES. SPECIFICATION CHANGES.
SET POINT CHANGES. TESTS AND EXPERIMENTS Completed During 1987 March 10. 1988 10 Pages t
IC0188-0014A-BT01
_2 FC-607: Replace Dies 41 Fire Pump Driver This modification replaced the diesel engine drive (Waukesha, Model No.
135-DKUSF) for fire pump (P-7) on the Fire Protection System with a compatible diesel engine drive (Caterpillar tractor, model no. 3208 NA-175). This change was due to the fact that the previous diesel engine drive required considerable raintenance and Waukesha Model no. 135-DKUSF is a discontinued model, making replacement parts unavailable.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
FC-610: EEQ Cable Replacement This Modification replaced electrical cables servicing EEQ equipment inside containment containing insulation types of either polyethylene or butyl rubber to alleviate NRC concerns over the qualification of these cables.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
FC-612 Modification of Walls of Kitchen and Zerox Room for Fire and Security Protection.
This change upgraded appropriate walls in the kitchen and Zerox Room in order to adequately serve as both fire and security barriers.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
Specification Changes (SC)
SC-84-015 This change involved the removal of a flovmeter transducer which was installed to check for leakage and check the calibration of the system flowmeter on the Stack Gas Monitoring System.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SC-85-003:
This change consisted of reaming the 1/2" hole for steam passage through the reactor depressurisation valve top to the pilot valve and countersinking at the exit. This was to eliminate or reduce reactor depressurization valve pilot leakage by eliminating oxidation which had occurred in this passage.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
IC0188-0014A-BT01 4
. . 3 SC-85-028:
This change consisted of modifying the fuel pool platform hoist controls to provide safety interlocks between associated contactor coils and overload protection on the slov speed vindings of the hoist motoi.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SC-85-031:
This change consisted of the repainting, demarcation and labeling of control room panels and console. This change provides the operator with control room panels and consoles that have controls demarcated and labeled by systems for rapid identification thereby minimizing human error, enhancing recognition of controls and improving operator response time. This change was part of the overall Detailed Control Room Design Review (DCRDR) at Big Rock Point.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SC-86-002:
This change consisted of replacement of the pressure transmitter (PT-153; steam to IP heater) in the HED System (extraction - water drains). This change was necessary due to unavailability of spare parts for repair.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SC-86-005:
This change consisted of the injection of sealant in the packing chamber in addition to the packing rings as a temporary repair of a steam leak on the steam to steam seal regulator and air ejector control valve. In addition, a shutoff adapter was installed on the valve.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SC-86-009 This change consisted of the injection of sealant in the packing chamber in addition to the packing rings as a temporary repair of a steam leak to the bypass valve for the main steam to ejector valve on the Air Ejector System. In addition, a shutoff adapter was installed.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
IC0188-0014A-BT01
. . 4 SC-86-010:
This change involved replacing two Asco solenoid valves on the containment Isolation System. Electrical Equipment Qualification (EEQ) file 4.45 requires replacement of seals, 0-rings ete on a four year interval and Big Rock Point was unable to obtain replacement kits for the original Asco solenoid valves.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SC-86-011:
This change, involved the replacement of the condenser fill line control valve (CV-4009) with a new type butterfly valve. The unavailability of replacement parts and the fact that the manufacturer discontinued this model necessitated this change.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SC-86-012:
This change consisted of the injection of sealant in the packing area as a temporary repair of a steam leak on the turbine bypass varmup control valve.
In addition, a shutoff adapter was installed.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SC-86-018:
This change involved a change in the original requirements for replacement
- control blades from 304 stainless steel sheath, standard all B C absorber 4
material, stellite roller pins and rollers to high purity 348 stainless steel sheath, hybrid hafnium - B4 C absorber material. Inconel X-750 roller pins and rollers.
The safety evaluation concluded that this change did not constitute an unreviewed I safety question. This change was also reviewed and approved by the h'RC and
) issued as Amendment 88 to the Technical Specifications.
1 SC-86-019:
This change consisted of replacement of the Limitorque valve operator (V0P-7068),
model SHA-00-5. for the backup enclosure sprays on the Post Incident System with a model SMB-00. This change was necessary to meet Electrical Equipment Qualification (EEQ) requirements.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
IC0188-0014A-BT01 l
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5 SC-86-020:
This change involved the replacement of ethylene propylene elastomers with viton elastomers in the solenoid valves on the Reactor Depressurization System Target Rock valves. This change was necessitated by the incompatibility of valve parts in an oil environment.
The safety evaluation concluded that this et.ange did not constitute an unreviewed safety question.
SC-86-021:
I This change consisted of three parts affecting the Reactor Depressurization f System. First, to replace the reactor depressurization carbon steel valve -
tops with the new stainless steel tops and allow the use of either the nev 4 tops or the original carbon steel tops. The use of the stainless steel tops was to reduce the possibility of corrosion product intrusion into the pilot valve during testing causing sutsequent valve leakage. Second, to allow a redesigned pilot valve assembly to be used on the reactor depressurization valves or the original designed pilot valve assembly. The use of the new pilot valve assembly was evaluated to eliminate the start of leakage and if leakage started. to reduce erosion of the pilot disc. The use of the re- .
designed pilot valve vill also improve the availability of spare / replacement rarts. Third, to allow the use of substitute stud bolts in lieu of using the original hex bolts. Design joint elamp load vill more closely be achieved during torquing operation following valve maintenance with the use of the new stud bolts.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SC-86-022:
This change consisted of the injection of sealant in the packing area to stop a steam leak on an isolation valve (VAE-28) on the Air Ejector System steam to steam seal regulator and air ejector control valve (CV-4104). In addition, a shutoff adapter was installed on the valve body.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SC-86-023:
This change consisted of raising the diesel fire pump centrol panel (C09) ten inches above the floor level (583'6") in the Screenhouse. This change was necessary because of the potential flooding of the Screenhouse due to increasing lake levels of Lake Michigan.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
IC0188-0014A-BT01 I
SC-86-025:
This change consisted of part number changes only to the control rod drive scram accumulator tank to concur with manufacturer's part number changes.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SC-87-001:
This change consisted of installation of a relay to provide clean-up pump control circuit trip and associated annunciation. This change was necessary to prevent the inadvertent reopening of the control valve (CV-4042; reactor water to clean-up domin) when the control pump circuit is in the "bypass" mode and the circuit has been interrupted by a high temperature trip signal.
! The safety evaluation concluded that this change did not constitute an unreviewed safety question.
l l SC-87-002: ,
This change consisted of removing the electric heater within the limitsvitch
! compattaent of Limitorque operator (V0P-70668 fire water to core spray hett l exchanger). This change was a result of NRC IEN 86-71.
The safety evaluation concluded that this change did not constitute an unreviss'd i safety question.
SC-87-003:
This change involved the Cycle 22 reload. The new fuel falls within previously l
docketed designs. Reconstituted fuel assemblies are in accordance with Consumers Power Company guidelines and are consistent with previous low power design.
The safety evaluation concluded that this change did not constitute an unreviewed safety question. The change was also reviewed and approved by the NRC and issued as Amendment 89 to the Technical Specifications.
SC-87-004 & SC-87-005:
This change involved the Cycle 22 reload core data, control blade shuffle and shutdown margin verification; low power physics testing. Cycle 22 has been determined by review of Cycle 17 reference and accident and transient analysis to comply with Technical Specification limits.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
IC0188-0014A-BT01
. . 7 SC-87-006:
This change consisted 19 a change of the stem material on Powell valve fig.
11323WE by the manufacturer. This change of material was due to the better machining characteristics and provides increased ductility of the new material.
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The safety evaluation concluded that this change did not constitute an unreviewed safety question.
This change involved the seal welding of a union downstream of VNS-0142 on the recirculating pump's drain header. This change was necessary to avoid joint leakage.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
I SC-87-008:
This change consisted of replacement of the instrument air containment isolation check valve (VA-0304) on the Service and Instrument Air System with a new Mark f270 check valve instead of the Mark #263. This change was necessary due to the unacceptable leak rate of VA-0304. This Specification Change also allows l the use of either the Mark #263 or the Mark #270 check valve on either VA-0304 or VA-0300 (service air containment isolation check valve).
4 The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SC-87-009:
, This change involved the replacement of the adjustment screw and the drilling i and tapping of the spring barrel to allow use of the new adjustment screw on the steam to steam seal regulator and air ejector control valve (CV-4104).
The original requirements for the screw were changed from 1-3/4" - 12 threads per inch plain carbon steel (1018 or 1020) to 2" - 12 threads per inch 6150 SAE alloy steel. This change was necessary because the adjustment screw was worn / damaged.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SC-87-010:
This change consisted of replacement of Station Power System 480V ac circuit breaker 052-1C14V. which failed during testing, with an equivalent type unit.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
IC0188-0014A-BT01
, . 8 SC-87-Oll:
This change involved the installation of a root valve and a test tap for each i turbine thrust bearing failure trip switch to permit verification of trip !
settings of the turbine thrust bearing failure switches with the turbine -
operating.
The safety evaluation concluded that this change did not constitute an unreviewed !
safety question.
SC-87-012:
i This change involved the replacement of the air actuator of the control valve (CV-4090) on the line for domin water to control rod drive pumps. The original actuator was leaking air and required replacement.
- The safety evaluation concluded that this change did not constitute an unreviewed safety question. ;
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SC-87-014: .
This change consisted of the injection of sealant in the packing shamber in addition to the packing rings as a temporary repair of a steam leak to the ;
bypass valve (VAE-3) for the main steam to ejector valve on the Air Ejector _
l System. In addition, a shutoff adapter was installed.
t The safety evaluation concluded that this change did not constitute an unreviewed safety question. ,
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SC-87-016: i This change consisted of the injection of sealant in the packing chamber in addition to the packing rings as a temporary repair of a steam leak to an isolation valve for a flow transmitter on the feedvater system. In addition, ,
a shutoff adapter was installed.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
' I SC-87-018:
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Thfs change consisted of the injection of sealant in the seating area as a temporary repair of a downstream nitrogen test connection valve (VRDS-103C) on ;
the Reactor Depressurization System. l The safety evaluation concluded that this change did not constitute an unreviewed safety question. [
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IC0188-0014A-BT01 [
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SC-87-021:
This change consisted of injection of sealant in addition to the packing rings as a temporary repair of a leak to a differential pressure transmitter and pressure indicator sensing valve on the reciretlating pump discharge on the Primary Coolant System.
The safety evaluation concluded that this change did not constitute an unreviewed safety quwstion.
SC-87-025:
This change consisted of a change to allow the use of a 12-UNT-2A & 2B thread fit for the stud and nut assembly for the Reactor Depressurization System valve flange tops in lieu of the 12-UNT-3A & 3B thread fit to minimize galling and seizing of the fasteners.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SC-87-026:
This change consisted of the addition of a flange to the emergency condenser !
vent piping to facilitate a means for pressurizing the shell side of the emergency condenser. This was used during leakage testing of the emergency condenser.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SC-87-028:
This change increased the operating vent orifice size on the low pressure heater to increase the heat exchange capacity.
L The safety evaluation concludea that this change did not constitute an unreviewed t safety question.
1 Set Point Change (SPC):
SPC-86-002:
This Change consisted of lowering the domestic water accumulator operating pressure shut-off from 85 psig rising to 75 psig rising. This change was necessary due to the difficulty the domestic water pump was having in overcoming the air pressure in the accumulator and causing the pump to operate nearly continuously.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
IC0188-0014A-BT01 I
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10 SPC-86-004:
This change involved teeporarily lowering the set point on the make-up demin conductivity switch to evaluate if the new setting would help to minimize the possibility of silica entering the make-up water. Reference SPC-87-001 The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SPC-87-001:
This change involved lowering the set point on the make-up demin conductivity i switch to minimize the possibility of silica entering the make-up water.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SPC-87-002:
This change involved an increase to the poison air supply low pressure alarm setting on the Liquid Poison System as an interim compensatory ceasure due to safety valve set point problems disucased in BRP LER 87-003. In the event the Liquid Poison System is required during an anticipated transient without scram, this change vill ensure sufficient nitrogen volume is available to establish a siphon of the liquid poison if the steam drum relief valves open at a higher than expected pressure.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SPC-87-003:
This change involved temporarily raising the alarm set point on the Containment Building 660' elevation condenser level reference temperature due to increase in localized ambient temperature. This alleviated a nuisance alarm condition on a shared annunciator.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SPECIAL SITE TEST (SST)
SST-36:
This test consisted of stroking Target Rock Reactor Depressurization Valve A (SV-4984) at an elevated temperature and pressure to determine if internal leakage would be reduced when the main and pilot valves discs re-seated.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
IC0188-0014A-BT01
ATTACHMENT II Consumers Power Company Big Rock Point Plant Docket 50-155 1987 PROCEDURE CHANCES REPORTABl.E TO Tile NRC Harch 10, 1988 ;
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Procedure RP-42: SCBA Cascade Recharging This procedure was deleted from the Health Physics department and is now performed by the Operations department.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
Procedure SOP-2: Refueling Operations This procedure change involved wording changes to plant requirements to clarify containment integrity as referenced in Technical Specification 1.2.3 during refueling operation.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
Procedure SOP-44: Spent Fuel Pool Operations and New Fuel Handling This procedure change involved wording changes to plant requirements to .
clarify containment integrity as referenced in Technical Specification 1.2.3 during spent fuel pool operations and new fuel handling. This change also added an additional step to define activities that are permitted without full co.ntainment integrity.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
Procedure TR-65ASD: Alternate Shutdown Battery Service Test This procedure change involved adjusting the service test load profile step currents to simulate the load currents required at 25'F and including the temperature correction factors for current adjustment when the battery is tested at electrolyte temperatures other than 77'F per the guidelines established in IEEE-450-1980. Other minor changes to the procedure consisted of title changes and editorial corrections to reflect organizational changes and gain additional information on individual cell voltages.
The safety evaluation concluded that this procedure did not constitute an unreviewed safety question.
Procedure TR-65S: Station Battery Service Test This procedure change involved reworking calculations to incorporate temperature current correction factor per IEEE-450-1980 and new load profile requirements.
Other minor changes to the procedures consisted basically of editorial corree-tions and procedural control requirements.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
IC0188-0014A-BT01
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.\ l Procedure TR-99 Surveillance-Check of ASD System Equipment This procedure change involved incorporating a step that will allow the calibration points (setpoints) of the emergency condenser instrumentation LS-3549 and LS-3550 to be verified.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
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e o Consumers
@ POWERING MKNIGAN'S PROGRES5 Power General Offices: 1945 West Parnall Road, Jackson, MI 49201 * (517) 788-05S0 March 10, 1988 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT -
1987 ANNUAL REPORT OF FACILITY CHANGES, TESTS AND EXPERIMENTS Attached is Consumers Power Company's Annual Report describing the Facility Changes (FC), Specification Changes (SC), Set Point Changes (SPC), tests and experiments performed at the Big Rock Point Plant in 1987. This report is submitted in accordance with the provisions of 10CFR50.59(b)',2). This report has two sections:
- 1. Those Facility Changes, Specification Changes, Set Point Changes, tests and experiments completed in 1987.
- 2. 1987 Procedure Changes reportable to the NRC.
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Ralp R Fr' isch Senior Licensing Analyst CC Administrator, Region III, NRC NRC Resident Inspector - Big Rock Point Plant Attachment OC0288-0036-NLO4 l